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You searched for subject:(Nuclear Graphite). Showing records 1 – 30 of 64 total matches.

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University of Pretoria

1. Murovhi, Phathutshedzo. Low temperature thermal properties of HTR nuclear fuel composite graphite.

Degree: Physics, 2013, University of Pretoria

Graphite and graphite composite materials are of great importance in various applications; however, they have been widely used in nuclear applications. Primarily in nuclear applications… (more)

Subjects/Keywords: Graphite; Graphite composite materials; Nuclear applications; UCTD

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APA (6th Edition):

Murovhi, P. (2013). Low temperature thermal properties of HTR nuclear fuel composite graphite. (Masters Thesis). University of Pretoria. Retrieved from http://hdl.handle.net/2263/33156

Chicago Manual of Style (16th Edition):

Murovhi, Phathutshedzo. “Low temperature thermal properties of HTR nuclear fuel composite graphite.” 2013. Masters Thesis, University of Pretoria. Accessed January 18, 2021. http://hdl.handle.net/2263/33156.

MLA Handbook (7th Edition):

Murovhi, Phathutshedzo. “Low temperature thermal properties of HTR nuclear fuel composite graphite.” 2013. Web. 18 Jan 2021.

Vancouver:

Murovhi P. Low temperature thermal properties of HTR nuclear fuel composite graphite. [Internet] [Masters thesis]. University of Pretoria; 2013. [cited 2021 Jan 18]. Available from: http://hdl.handle.net/2263/33156.

Council of Science Editors:

Murovhi P. Low temperature thermal properties of HTR nuclear fuel composite graphite. [Masters Thesis]. University of Pretoria; 2013. Available from: http://hdl.handle.net/2263/33156


University of Manchester

2. Bodel, William. THE RELATIONSHIP BETWEEN MICROSTRUCTURE AND YOUNG’S MODULUS OF NUCLEAR GRAPHITE.

Degree: 2013, University of Manchester

 In addition to its role as moderator within British nuclear reactors, polycrystalline graphite is also a major structural component of the core, enabling access for… (more)

Subjects/Keywords: Nuclear; Graphite; Young's Modulus

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APA (6th Edition):

Bodel, W. (2013). THE RELATIONSHIP BETWEEN MICROSTRUCTURE AND YOUNG’S MODULUS OF NUCLEAR GRAPHITE. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:198592

Chicago Manual of Style (16th Edition):

Bodel, William. “THE RELATIONSHIP BETWEEN MICROSTRUCTURE AND YOUNG’S MODULUS OF NUCLEAR GRAPHITE.” 2013. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:198592.

MLA Handbook (7th Edition):

Bodel, William. “THE RELATIONSHIP BETWEEN MICROSTRUCTURE AND YOUNG’S MODULUS OF NUCLEAR GRAPHITE.” 2013. Web. 18 Jan 2021.

Vancouver:

Bodel W. THE RELATIONSHIP BETWEEN MICROSTRUCTURE AND YOUNG’S MODULUS OF NUCLEAR GRAPHITE. [Internet] [Doctoral dissertation]. University of Manchester; 2013. [cited 2021 Jan 18]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:198592.

Council of Science Editors:

Bodel W. THE RELATIONSHIP BETWEEN MICROSTRUCTURE AND YOUNG’S MODULUS OF NUCLEAR GRAPHITE. [Doctoral Dissertation]. University of Manchester; 2013. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:198592


University of Manchester

3. Morrison, Craig Neil. Lattice-Modelling of Nuclear Graphite for Improved Understanding of Fracture Processes.

Degree: 2016, University of Manchester

 The integrity of graphite components is critical for their fitness for purpose. Since graphite is a quasi-brittle material the dominant mechanism for loss of integrity… (more)

Subjects/Keywords: nuclear graphite; lattice modelling

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APA (6th Edition):

Morrison, C. N. (2016). Lattice-Modelling of Nuclear Graphite for Improved Understanding of Fracture Processes. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:299976

Chicago Manual of Style (16th Edition):

Morrison, Craig Neil. “Lattice-Modelling of Nuclear Graphite for Improved Understanding of Fracture Processes.” 2016. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:299976.

MLA Handbook (7th Edition):

Morrison, Craig Neil. “Lattice-Modelling of Nuclear Graphite for Improved Understanding of Fracture Processes.” 2016. Web. 18 Jan 2021.

Vancouver:

Morrison CN. Lattice-Modelling of Nuclear Graphite for Improved Understanding of Fracture Processes. [Internet] [Doctoral dissertation]. University of Manchester; 2016. [cited 2021 Jan 18]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:299976.

Council of Science Editors:

Morrison CN. Lattice-Modelling of Nuclear Graphite for Improved Understanding of Fracture Processes. [Doctoral Dissertation]. University of Manchester; 2016. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:299976


University of Plymouth

4. Jones, Katie. A study of the effects of irradiation and radiolytic oxidation of the pore-level structure of gilsocarbon nuclear graphite.

Degree: PhD, 2019, University of Plymouth

 The pore-level characterisation of nuclear graphite is critical for predicting reactor safety and for assessing the viability of different grades of graphite material. The majority… (more)

Subjects/Keywords: Nuclear Graphite; Characterisation; Porosity

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APA (6th Edition):

Jones, K. (2019). A study of the effects of irradiation and radiolytic oxidation of the pore-level structure of gilsocarbon nuclear graphite. (Doctoral Dissertation). University of Plymouth. Retrieved from http://hdl.handle.net/10026.1/13436

Chicago Manual of Style (16th Edition):

Jones, Katie. “A study of the effects of irradiation and radiolytic oxidation of the pore-level structure of gilsocarbon nuclear graphite.” 2019. Doctoral Dissertation, University of Plymouth. Accessed January 18, 2021. http://hdl.handle.net/10026.1/13436.

MLA Handbook (7th Edition):

Jones, Katie. “A study of the effects of irradiation and radiolytic oxidation of the pore-level structure of gilsocarbon nuclear graphite.” 2019. Web. 18 Jan 2021.

Vancouver:

Jones K. A study of the effects of irradiation and radiolytic oxidation of the pore-level structure of gilsocarbon nuclear graphite. [Internet] [Doctoral dissertation]. University of Plymouth; 2019. [cited 2021 Jan 18]. Available from: http://hdl.handle.net/10026.1/13436.

Council of Science Editors:

Jones K. A study of the effects of irradiation and radiolytic oxidation of the pore-level structure of gilsocarbon nuclear graphite. [Doctoral Dissertation]. University of Plymouth; 2019. Available from: http://hdl.handle.net/10026.1/13436


University of Manchester

5. Bodel, William. The relationship between microstructure and Young's modulus of nuclear graphite.

Degree: Thesis (Eng.D.), 2013, University of Manchester

 In addition to its role as moderator within British nuclear reactors, polycrystalline graphite is also a major structural component of the core, enabling access for… (more)

Subjects/Keywords: 553.2; Nuclear; Graphite; Young's Modulus

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APA (6th Edition):

Bodel, W. (2013). The relationship between microstructure and Young's modulus of nuclear graphite. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/the-relationship-between-microstructure-and-youngs-modulus-of-nuclear-graphite(ac5fe868-cefb-4f0c-8b22-a8904bc97da5).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.576873

Chicago Manual of Style (16th Edition):

Bodel, William. “The relationship between microstructure and Young's modulus of nuclear graphite.” 2013. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. https://www.research.manchester.ac.uk/portal/en/theses/the-relationship-between-microstructure-and-youngs-modulus-of-nuclear-graphite(ac5fe868-cefb-4f0c-8b22-a8904bc97da5).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.576873.

MLA Handbook (7th Edition):

Bodel, William. “The relationship between microstructure and Young's modulus of nuclear graphite.” 2013. Web. 18 Jan 2021.

Vancouver:

Bodel W. The relationship between microstructure and Young's modulus of nuclear graphite. [Internet] [Doctoral dissertation]. University of Manchester; 2013. [cited 2021 Jan 18]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/the-relationship-between-microstructure-and-youngs-modulus-of-nuclear-graphite(ac5fe868-cefb-4f0c-8b22-a8904bc97da5).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.576873.

Council of Science Editors:

Bodel W. The relationship between microstructure and Young's modulus of nuclear graphite. [Doctoral Dissertation]. University of Manchester; 2013. Available from: https://www.research.manchester.ac.uk/portal/en/theses/the-relationship-between-microstructure-and-youngs-modulus-of-nuclear-graphite(ac5fe868-cefb-4f0c-8b22-a8904bc97da5).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.576873


University of Manchester

6. Morrison, Craig Neil. Lattice-modelling of nuclear graphite for improved understanding of fracture processes.

Degree: PhD, 2016, University of Manchester

 The integrity of graphite components is critical for their fitness for purpose. Since graphite is a quasi-brittle material the dominant mechanism for loss of integrity… (more)

Subjects/Keywords: 620.1; nuclear graphite; lattice modelling

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APA (6th Edition):

Morrison, C. N. (2016). Lattice-modelling of nuclear graphite for improved understanding of fracture processes. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/latticemodelling-of-nuclear-graphite-for-improved-understanding-of-fracture-processes(10b302d1-88fb-466b-9030-d34b4fc33293).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.706240

Chicago Manual of Style (16th Edition):

Morrison, Craig Neil. “Lattice-modelling of nuclear graphite for improved understanding of fracture processes.” 2016. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. https://www.research.manchester.ac.uk/portal/en/theses/latticemodelling-of-nuclear-graphite-for-improved-understanding-of-fracture-processes(10b302d1-88fb-466b-9030-d34b4fc33293).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.706240.

MLA Handbook (7th Edition):

Morrison, Craig Neil. “Lattice-modelling of nuclear graphite for improved understanding of fracture processes.” 2016. Web. 18 Jan 2021.

Vancouver:

Morrison CN. Lattice-modelling of nuclear graphite for improved understanding of fracture processes. [Internet] [Doctoral dissertation]. University of Manchester; 2016. [cited 2021 Jan 18]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/latticemodelling-of-nuclear-graphite-for-improved-understanding-of-fracture-processes(10b302d1-88fb-466b-9030-d34b4fc33293).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.706240.

Council of Science Editors:

Morrison CN. Lattice-modelling of nuclear graphite for improved understanding of fracture processes. [Doctoral Dissertation]. University of Manchester; 2016. Available from: https://www.research.manchester.ac.uk/portal/en/theses/latticemodelling-of-nuclear-graphite-for-improved-understanding-of-fracture-processes(10b302d1-88fb-466b-9030-d34b4fc33293).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.706240


University of Manchester

7. Worth, Robert Numa. Thermal Treatment of Oldbury Magnox Reactor Irradiated Graphite.

Degree: 2016, University of Manchester

 THERMAL TREATMENT OF OLDBURY MAGNOX REACTOR IRRADIATED GRAPHITEApproximately 96,000 tonnes of the UK Higher Activity Waste (HAW) inventory consists of irradiated nuclear graphite. The current… (more)

Subjects/Keywords: carbon-14; nuclear graphite; irradiated graphite; thermal treatment; waste

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APA (6th Edition):

Worth, R. N. (2016). Thermal Treatment of Oldbury Magnox Reactor Irradiated Graphite. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:301365

Chicago Manual of Style (16th Edition):

Worth, Robert Numa. “Thermal Treatment of Oldbury Magnox Reactor Irradiated Graphite.” 2016. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:301365.

MLA Handbook (7th Edition):

Worth, Robert Numa. “Thermal Treatment of Oldbury Magnox Reactor Irradiated Graphite.” 2016. Web. 18 Jan 2021.

Vancouver:

Worth RN. Thermal Treatment of Oldbury Magnox Reactor Irradiated Graphite. [Internet] [Doctoral dissertation]. University of Manchester; 2016. [cited 2021 Jan 18]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:301365.

Council of Science Editors:

Worth RN. Thermal Treatment of Oldbury Magnox Reactor Irradiated Graphite. [Doctoral Dissertation]. University of Manchester; 2016. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:301365


University of Manchester

8. Mcdermott, Lorraine. Characterisation and chemical treatment of irradiated UK graphite waste.

Degree: PhD, 2012, University of Manchester

 Once current nuclear reactor operation ceases in the U.K. there will be an estimated 99,000 tonnes of irradiated nuclear graphite waste which may account for… (more)

Subjects/Keywords: 621.4838; Nuclear Graphite; Chemical Treatment; Leaching; Characterisation

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APA (6th Edition):

Mcdermott, L. (2012). Characterisation and chemical treatment of irradiated UK graphite waste. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/characterisation-and-chemical-treatment-of-irradiated-uk-graphite-waste(11852bdd-2c37-4361-ad0f-0554d05782e2).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.553504

Chicago Manual of Style (16th Edition):

Mcdermott, Lorraine. “Characterisation and chemical treatment of irradiated UK graphite waste.” 2012. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. https://www.research.manchester.ac.uk/portal/en/theses/characterisation-and-chemical-treatment-of-irradiated-uk-graphite-waste(11852bdd-2c37-4361-ad0f-0554d05782e2).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.553504.

MLA Handbook (7th Edition):

Mcdermott, Lorraine. “Characterisation and chemical treatment of irradiated UK graphite waste.” 2012. Web. 18 Jan 2021.

Vancouver:

Mcdermott L. Characterisation and chemical treatment of irradiated UK graphite waste. [Internet] [Doctoral dissertation]. University of Manchester; 2012. [cited 2021 Jan 18]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/characterisation-and-chemical-treatment-of-irradiated-uk-graphite-waste(11852bdd-2c37-4361-ad0f-0554d05782e2).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.553504.

Council of Science Editors:

Mcdermott L. Characterisation and chemical treatment of irradiated UK graphite waste. [Doctoral Dissertation]. University of Manchester; 2012. Available from: https://www.research.manchester.ac.uk/portal/en/theses/characterisation-and-chemical-treatment-of-irradiated-uk-graphite-waste(11852bdd-2c37-4361-ad0f-0554d05782e2).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.553504


University of Missouri – Columbia

9. Troy, Raymond Steven. Generation of graphite particles by abrasion and their characterization.

Degree: 2015, University of Missouri – Columbia

 Characterization of graphite particles (dust) produced by abrasion that would occur in an operating pebble bed reactor is of interest for reasons of safety, operation,… (more)

Subjects/Keywords: Pebble bed reactors; Graphite; Nuclear power plants

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APA (6th Edition):

Troy, R. S. (2015). Generation of graphite particles by abrasion and their characterization. (Thesis). University of Missouri – Columbia. Retrieved from http://hdl.handle.net/10355/46903

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Troy, Raymond Steven. “Generation of graphite particles by abrasion and their characterization.” 2015. Thesis, University of Missouri – Columbia. Accessed January 18, 2021. http://hdl.handle.net/10355/46903.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Troy, Raymond Steven. “Generation of graphite particles by abrasion and their characterization.” 2015. Web. 18 Jan 2021.

Vancouver:

Troy RS. Generation of graphite particles by abrasion and their characterization. [Internet] [Thesis]. University of Missouri – Columbia; 2015. [cited 2021 Jan 18]. Available from: http://hdl.handle.net/10355/46903.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Troy RS. Generation of graphite particles by abrasion and their characterization. [Thesis]. University of Missouri – Columbia; 2015. Available from: http://hdl.handle.net/10355/46903

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of Pretoria

10. [No author]. Purifying coal for the production of nuclear graphite .

Degree: 2008, University of Pretoria

 Carbon materials play a fundamental role in the development of fusion reactors, for both the generation of electric power and the production of nuclear materials.… (more)

Subjects/Keywords: Purification; Nuclear graphite; Fusion reactors; Nuclear materials; UCTD

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APA (6th Edition):

author], [. (2008). Purifying coal for the production of nuclear graphite . (Masters Thesis). University of Pretoria. Retrieved from http://upetd.up.ac.za/thesis/available/etd-04212008-124149/

Chicago Manual of Style (16th Edition):

author], [No. “Purifying coal for the production of nuclear graphite .” 2008. Masters Thesis, University of Pretoria. Accessed January 18, 2021. http://upetd.up.ac.za/thesis/available/etd-04212008-124149/.

MLA Handbook (7th Edition):

author], [No. “Purifying coal for the production of nuclear graphite .” 2008. Web. 18 Jan 2021.

Vancouver:

author] [. Purifying coal for the production of nuclear graphite . [Internet] [Masters thesis]. University of Pretoria; 2008. [cited 2021 Jan 18]. Available from: http://upetd.up.ac.za/thesis/available/etd-04212008-124149/.

Council of Science Editors:

author] [. Purifying coal for the production of nuclear graphite . [Masters Thesis]. University of Pretoria; 2008. Available from: http://upetd.up.ac.za/thesis/available/etd-04212008-124149/


University of Pretoria

11. Phupheli, Milingoni Robert. Purifying coal for the production of nuclear graphite.

Degree: MSc, Chemistry, 2008, University of Pretoria

 Carbon materials play a fundamental role in the development of fusion reactors, for both the generation of electric power and the production of nuclear materials.… (more)

Subjects/Keywords: Purification; Nuclear graphite; Fusion reactors; Nuclear materials; UCTD

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APA (6th Edition):

Phupheli, M. (2008). Purifying coal for the production of nuclear graphite. (Masters Thesis). University of Pretoria. Retrieved from http://hdl.handle.net/2263/24051

Chicago Manual of Style (16th Edition):

Phupheli, Milingoni. “Purifying coal for the production of nuclear graphite.” 2008. Masters Thesis, University of Pretoria. Accessed January 18, 2021. http://hdl.handle.net/2263/24051.

MLA Handbook (7th Edition):

Phupheli, Milingoni. “Purifying coal for the production of nuclear graphite.” 2008. Web. 18 Jan 2021.

Vancouver:

Phupheli M. Purifying coal for the production of nuclear graphite. [Internet] [Masters thesis]. University of Pretoria; 2008. [cited 2021 Jan 18]. Available from: http://hdl.handle.net/2263/24051.

Council of Science Editors:

Phupheli M. Purifying coal for the production of nuclear graphite. [Masters Thesis]. University of Pretoria; 2008. Available from: http://hdl.handle.net/2263/24051


University of Manchester

12. Bakenne, Adetokunboh Temitope. DEFORMATION AND MODULUS CHANGES OF NUCLEAR GRAPHITE DUE TO HYDROSTATIC PRESSURE LOADING.

Degree: 2013, University of Manchester

Graphite is used within a reactor as a moderator and a reflector material. During fast neutron irradiation, the physical properties and dimensions of nuclear graphite(more)

Subjects/Keywords: Nuclear graphite; Irradiation; Virgin- unirradiated; Hydrostatic pressure; Young's moduli; Dynamic moduli; Graphite moderator

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APA (6th Edition):

Bakenne, A. T. (2013). DEFORMATION AND MODULUS CHANGES OF NUCLEAR GRAPHITE DUE TO HYDROSTATIC PRESSURE LOADING. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:193369

Chicago Manual of Style (16th Edition):

Bakenne, Adetokunboh Temitope. “DEFORMATION AND MODULUS CHANGES OF NUCLEAR GRAPHITE DUE TO HYDROSTATIC PRESSURE LOADING.” 2013. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:193369.

MLA Handbook (7th Edition):

Bakenne, Adetokunboh Temitope. “DEFORMATION AND MODULUS CHANGES OF NUCLEAR GRAPHITE DUE TO HYDROSTATIC PRESSURE LOADING.” 2013. Web. 18 Jan 2021.

Vancouver:

Bakenne AT. DEFORMATION AND MODULUS CHANGES OF NUCLEAR GRAPHITE DUE TO HYDROSTATIC PRESSURE LOADING. [Internet] [Doctoral dissertation]. University of Manchester; 2013. [cited 2021 Jan 18]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:193369.

Council of Science Editors:

Bakenne AT. DEFORMATION AND MODULUS CHANGES OF NUCLEAR GRAPHITE DUE TO HYDROSTATIC PRESSURE LOADING. [Doctoral Dissertation]. University of Manchester; 2013. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:193369


University of Manchester

13. Bakenne, Adetokunboh. Deformation and modulus changes of nuclear graphite due to hydrostatic pressure loading.

Degree: PhD, 2013, University of Manchester

Graphite is used within a reactor as a moderator and a reflector material. During fast neutron irradiation, the physical properties and dimensions of nuclear graphite(more)

Subjects/Keywords: 621.48; Graphite moderator; Dynamic moduli; Young's moduli; Nuclear graphite; Virgin- unirradiated; Irradiation; Hydrostatic pressure

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APA (6th Edition):

Bakenne, A. (2013). Deformation and modulus changes of nuclear graphite due to hydrostatic pressure loading. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/deformation-and-modulus-changes-of-nuclear-graphite-due-to-hydrostatic-pressure-loading(aa6b8fd6-1c9f-4e71-b0dc-b5150b67223d).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.740252

Chicago Manual of Style (16th Edition):

Bakenne, Adetokunboh. “Deformation and modulus changes of nuclear graphite due to hydrostatic pressure loading.” 2013. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. https://www.research.manchester.ac.uk/portal/en/theses/deformation-and-modulus-changes-of-nuclear-graphite-due-to-hydrostatic-pressure-loading(aa6b8fd6-1c9f-4e71-b0dc-b5150b67223d).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.740252.

MLA Handbook (7th Edition):

Bakenne, Adetokunboh. “Deformation and modulus changes of nuclear graphite due to hydrostatic pressure loading.” 2013. Web. 18 Jan 2021.

Vancouver:

Bakenne A. Deformation and modulus changes of nuclear graphite due to hydrostatic pressure loading. [Internet] [Doctoral dissertation]. University of Manchester; 2013. [cited 2021 Jan 18]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/deformation-and-modulus-changes-of-nuclear-graphite-due-to-hydrostatic-pressure-loading(aa6b8fd6-1c9f-4e71-b0dc-b5150b67223d).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.740252.

Council of Science Editors:

Bakenne A. Deformation and modulus changes of nuclear graphite due to hydrostatic pressure loading. [Doctoral Dissertation]. University of Manchester; 2013. Available from: https://www.research.manchester.ac.uk/portal/en/theses/deformation-and-modulus-changes-of-nuclear-graphite-due-to-hydrostatic-pressure-loading(aa6b8fd6-1c9f-4e71-b0dc-b5150b67223d).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.740252


North-West University

14. Markgraaff, Renier Francois. Relationship between the natural frequencies and fatigue life of NGB–18 graphite / Renier Markgraaff .

Degree: 2010, North-West University

 NBG–18 graphite is developed by SGL Carbon for the Pebble Bed Modular Reactor Company (PBMR), and is used as the preferred material for the internal… (more)

Subjects/Keywords: NGB-18 nuclear graphite; Hammer impulse excitation; Fatigue; Natural frequency; Relationship

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APA (6th Edition):

Markgraaff, R. F. (2010). Relationship between the natural frequencies and fatigue life of NGB–18 graphite / Renier Markgraaff . (Thesis). North-West University. Retrieved from http://hdl.handle.net/10394/4813

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Markgraaff, Renier Francois. “Relationship between the natural frequencies and fatigue life of NGB–18 graphite / Renier Markgraaff .” 2010. Thesis, North-West University. Accessed January 18, 2021. http://hdl.handle.net/10394/4813.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Markgraaff, Renier Francois. “Relationship between the natural frequencies and fatigue life of NGB–18 graphite / Renier Markgraaff .” 2010. Web. 18 Jan 2021.

Vancouver:

Markgraaff RF. Relationship between the natural frequencies and fatigue life of NGB–18 graphite / Renier Markgraaff . [Internet] [Thesis]. North-West University; 2010. [cited 2021 Jan 18]. Available from: http://hdl.handle.net/10394/4813.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Markgraaff RF. Relationship between the natural frequencies and fatigue life of NGB–18 graphite / Renier Markgraaff . [Thesis]. North-West University; 2010. Available from: http://hdl.handle.net/10394/4813

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of Manchester

15. Turner, Joel David. The performance of a nuclear fuel-matrix material in a sealed CO₂ system.

Degree: PhD, 2013, University of Manchester

 An advanced concept high temperature reactor (HTR) design has been proposed - The ‘U-Battery’, which utilises a unique sealed coolant loop, and is intended to… (more)

Subjects/Keywords: 621.48; Nuclear Graphite; Oxidation; High Temperature Reactor; TRISO

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APA (6th Edition):

Turner, J. D. (2013). The performance of a nuclear fuel-matrix material in a sealed CO₂ system. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/the-performance-of-a-nuclear-fuelmatrix-material-in-a-sealed-co2-system(caaeee7f-9551-485b-b3dc-fe14e75bcc5a).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566529

Chicago Manual of Style (16th Edition):

Turner, Joel David. “The performance of a nuclear fuel-matrix material in a sealed CO₂ system.” 2013. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. https://www.research.manchester.ac.uk/portal/en/theses/the-performance-of-a-nuclear-fuelmatrix-material-in-a-sealed-co2-system(caaeee7f-9551-485b-b3dc-fe14e75bcc5a).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566529.

MLA Handbook (7th Edition):

Turner, Joel David. “The performance of a nuclear fuel-matrix material in a sealed CO₂ system.” 2013. Web. 18 Jan 2021.

Vancouver:

Turner JD. The performance of a nuclear fuel-matrix material in a sealed CO₂ system. [Internet] [Doctoral dissertation]. University of Manchester; 2013. [cited 2021 Jan 18]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/the-performance-of-a-nuclear-fuelmatrix-material-in-a-sealed-co2-system(caaeee7f-9551-485b-b3dc-fe14e75bcc5a).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566529.

Council of Science Editors:

Turner JD. The performance of a nuclear fuel-matrix material in a sealed CO₂ system. [Doctoral Dissertation]. University of Manchester; 2013. Available from: https://www.research.manchester.ac.uk/portal/en/theses/the-performance-of-a-nuclear-fuelmatrix-material-in-a-sealed-co2-system(caaeee7f-9551-485b-b3dc-fe14e75bcc5a).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566529


University of Manchester

16. Luyken, Lewis. Using intercalation to simulate irradiation damage of nuclear graphite.

Degree: PhD, 2012, University of Manchester

 This thesis investigates the use of bromine intercalation of graphite as a method to simulate and investigate irradiation damage. In particular this study investigates the… (more)

Subjects/Keywords: 620.1; Graphite; Nuclear; Intercalation; Dimensional Change; Young's Modulus

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APA (6th Edition):

Luyken, L. (2012). Using intercalation to simulate irradiation damage of nuclear graphite. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/using-intercalation-to-simulate-irradiation-damage-of-nuclear-graphite(85ce1ebb-2981-4807-8cf8-4aedc4acea97).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566532

Chicago Manual of Style (16th Edition):

Luyken, Lewis. “Using intercalation to simulate irradiation damage of nuclear graphite.” 2012. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. https://www.research.manchester.ac.uk/portal/en/theses/using-intercalation-to-simulate-irradiation-damage-of-nuclear-graphite(85ce1ebb-2981-4807-8cf8-4aedc4acea97).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566532.

MLA Handbook (7th Edition):

Luyken, Lewis. “Using intercalation to simulate irradiation damage of nuclear graphite.” 2012. Web. 18 Jan 2021.

Vancouver:

Luyken L. Using intercalation to simulate irradiation damage of nuclear graphite. [Internet] [Doctoral dissertation]. University of Manchester; 2012. [cited 2021 Jan 18]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/using-intercalation-to-simulate-irradiation-damage-of-nuclear-graphite(85ce1ebb-2981-4807-8cf8-4aedc4acea97).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566532.

Council of Science Editors:

Luyken L. Using intercalation to simulate irradiation damage of nuclear graphite. [Doctoral Dissertation]. University of Manchester; 2012. Available from: https://www.research.manchester.ac.uk/portal/en/theses/using-intercalation-to-simulate-irradiation-damage-of-nuclear-graphite(85ce1ebb-2981-4807-8cf8-4aedc4acea97).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566532


University of Manchester

17. Fletcher, Adam. Non-destructive testing of the graphite core within an advanced gas-cooled reactor.

Degree: Thesis (Eng.D.), 2014, University of Manchester

 The aim of this work has been to apply the techniques of non-destructive testing and evaluation to the graphite fuel channel bricks which form the… (more)

Subjects/Keywords: 621.382; nuclear; graphite; electromagnetic; ndt; finite element; modelling; eddy current

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APA (6th Edition):

Fletcher, A. (2014). Non-destructive testing of the graphite core within an advanced gas-cooled reactor. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/nondestructive-testing-of-the-graphite-core-within-an-advanced-gascooled-reactor(3ca5c904-6860-46b8-8538-4136cb2aedcd).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.634878

Chicago Manual of Style (16th Edition):

Fletcher, Adam. “Non-destructive testing of the graphite core within an advanced gas-cooled reactor.” 2014. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. https://www.research.manchester.ac.uk/portal/en/theses/nondestructive-testing-of-the-graphite-core-within-an-advanced-gascooled-reactor(3ca5c904-6860-46b8-8538-4136cb2aedcd).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.634878.

MLA Handbook (7th Edition):

Fletcher, Adam. “Non-destructive testing of the graphite core within an advanced gas-cooled reactor.” 2014. Web. 18 Jan 2021.

Vancouver:

Fletcher A. Non-destructive testing of the graphite core within an advanced gas-cooled reactor. [Internet] [Doctoral dissertation]. University of Manchester; 2014. [cited 2021 Jan 18]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/nondestructive-testing-of-the-graphite-core-within-an-advanced-gascooled-reactor(3ca5c904-6860-46b8-8538-4136cb2aedcd).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.634878.

Council of Science Editors:

Fletcher A. Non-destructive testing of the graphite core within an advanced gas-cooled reactor. [Doctoral Dissertation]. University of Manchester; 2014. Available from: https://www.research.manchester.ac.uk/portal/en/theses/nondestructive-testing-of-the-graphite-core-within-an-advanced-gascooled-reactor(3ca5c904-6860-46b8-8538-4136cb2aedcd).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.634878


University of Manchester

18. Black, Greg. Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal.

Degree: Thesis (Eng.D.), 2014, University of Manchester

 The University of Manchester Greg BlackThesis submitted for the degree of Doctor of EngineeringIrradiated Graphite Waste: Analysis and Modelling of Radionuclide Production with a View… (more)

Subjects/Keywords: 621.48; Nuclear Graphite; Radioactive Waste Management; Reactor Physics Modelling; Gamma Spectroscopy

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APA (6th Edition):

Black, G. (2014). Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/irradiated-graphite-waste-analysis-and-modelling-of-radionuclide-production-with-a-view-to-long-term-disposal(9993a76a-15c6-4cbe-a4a3-4c0bc88c3134).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.664547

Chicago Manual of Style (16th Edition):

Black, Greg. “Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal.” 2014. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. https://www.research.manchester.ac.uk/portal/en/theses/irradiated-graphite-waste-analysis-and-modelling-of-radionuclide-production-with-a-view-to-long-term-disposal(9993a76a-15c6-4cbe-a4a3-4c0bc88c3134).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.664547.

MLA Handbook (7th Edition):

Black, Greg. “Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal.” 2014. Web. 18 Jan 2021.

Vancouver:

Black G. Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal. [Internet] [Doctoral dissertation]. University of Manchester; 2014. [cited 2021 Jan 18]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/irradiated-graphite-waste-analysis-and-modelling-of-radionuclide-production-with-a-view-to-long-term-disposal(9993a76a-15c6-4cbe-a4a3-4c0bc88c3134).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.664547.

Council of Science Editors:

Black G. Irradiated graphite waste : analysis and modelling of radionuclide production with a view to long term disposal. [Doctoral Dissertation]. University of Manchester; 2014. Available from: https://www.research.manchester.ac.uk/portal/en/theses/irradiated-graphite-waste-analysis-and-modelling-of-radionuclide-production-with-a-view-to-long-term-disposal(9993a76a-15c6-4cbe-a4a3-4c0bc88c3134).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.664547


Kansas State University

19. Gould, Daniel W. Air Ingress in HTGRs: the process, effects, and experimental methods relating to its investigation and consequences.

Degree: PhD, Department of Mechanical and Nuclear Engineering, 2018, Kansas State University

 Helium-cooled, graphite moderated reactors have been considered for a future fleet of high temperature and high efficiency nuclear power plants. Nuclear-grade graphite is used in… (more)

Subjects/Keywords: HTGR; Air Ingress; Onset of Natural Convection; graphite; oxidation; nuclear reactor

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APA (6th Edition):

Gould, D. W. (2018). Air Ingress in HTGRs: the process, effects, and experimental methods relating to its investigation and consequences. (Doctoral Dissertation). Kansas State University. Retrieved from http://hdl.handle.net/2097/39294

Chicago Manual of Style (16th Edition):

Gould, Daniel W. “Air Ingress in HTGRs: the process, effects, and experimental methods relating to its investigation and consequences.” 2018. Doctoral Dissertation, Kansas State University. Accessed January 18, 2021. http://hdl.handle.net/2097/39294.

MLA Handbook (7th Edition):

Gould, Daniel W. “Air Ingress in HTGRs: the process, effects, and experimental methods relating to its investigation and consequences.” 2018. Web. 18 Jan 2021.

Vancouver:

Gould DW. Air Ingress in HTGRs: the process, effects, and experimental methods relating to its investigation and consequences. [Internet] [Doctoral dissertation]. Kansas State University; 2018. [cited 2021 Jan 18]. Available from: http://hdl.handle.net/2097/39294.

Council of Science Editors:

Gould DW. Air Ingress in HTGRs: the process, effects, and experimental methods relating to its investigation and consequences. [Doctoral Dissertation]. Kansas State University; 2018. Available from: http://hdl.handle.net/2097/39294


University of Texas – Austin

20. Hill, Jason Edward, 1978-. One-dimensional electron systems on graphene edges.

Degree: PhD, Physics, 2007, University of Texas – Austin

 In this dissertation several aspects on one-dimensional edge states in grapheme are studied. First, a background in the history and development of graphitic forms is… (more)

Subjects/Keywords: Graphite; Nanostructured materials; Nuclear spin

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APA (6th Edition):

Hill, Jason Edward, 1. (2007). One-dimensional electron systems on graphene edges. (Doctoral Dissertation). University of Texas – Austin. Retrieved from http://hdl.handle.net/2152/3797

Chicago Manual of Style (16th Edition):

Hill, Jason Edward, 1978-. “One-dimensional electron systems on graphene edges.” 2007. Doctoral Dissertation, University of Texas – Austin. Accessed January 18, 2021. http://hdl.handle.net/2152/3797.

MLA Handbook (7th Edition):

Hill, Jason Edward, 1978-. “One-dimensional electron systems on graphene edges.” 2007. Web. 18 Jan 2021.

Vancouver:

Hill, Jason Edward 1. One-dimensional electron systems on graphene edges. [Internet] [Doctoral dissertation]. University of Texas – Austin; 2007. [cited 2021 Jan 18]. Available from: http://hdl.handle.net/2152/3797.

Council of Science Editors:

Hill, Jason Edward 1. One-dimensional electron systems on graphene edges. [Doctoral Dissertation]. University of Texas – Austin; 2007. Available from: http://hdl.handle.net/2152/3797

21. Blondel, Antoine. Effets de la température et de l’irradiation sur le comportement du chlore 37 dans le graphite nucléaire : conséquences sur la mobilité du chlore 36 dans les graphites irradiés : Effects of the temperature and the irradiation on the behaviour of chlorine 37 in nuclear graphite : consequences on the mobility of chlorine 36 in irradiated graphites.

Degree: Docteur es, Physique-Chimie, 2013, Université Claude Bernard – Lyon I

Ce travail s'inscrit dans le cadre des études sur la gestion des déchets graphités issus du démantèlement des centrales UNGG (Uranium Naturel Graphite Gaz). Les… (more)

Subjects/Keywords: Graphite; Nucléaire; Irradiation; Température; Chlore; Comportement; UNGG; Implantation; Graphite; Nuclear; Irradiation; Temperature; Chlorine; Behaviour; UNGG; Implantation; 539.7

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APA (6th Edition):

Blondel, A. (2013). Effets de la température et de l’irradiation sur le comportement du chlore 37 dans le graphite nucléaire : conséquences sur la mobilité du chlore 36 dans les graphites irradiés : Effects of the temperature and the irradiation on the behaviour of chlorine 37 in nuclear graphite : consequences on the mobility of chlorine 36 in irradiated graphites. (Doctoral Dissertation). Université Claude Bernard – Lyon I. Retrieved from http://www.theses.fr/2013LYO10323

Chicago Manual of Style (16th Edition):

Blondel, Antoine. “Effets de la température et de l’irradiation sur le comportement du chlore 37 dans le graphite nucléaire : conséquences sur la mobilité du chlore 36 dans les graphites irradiés : Effects of the temperature and the irradiation on the behaviour of chlorine 37 in nuclear graphite : consequences on the mobility of chlorine 36 in irradiated graphites.” 2013. Doctoral Dissertation, Université Claude Bernard – Lyon I. Accessed January 18, 2021. http://www.theses.fr/2013LYO10323.

MLA Handbook (7th Edition):

Blondel, Antoine. “Effets de la température et de l’irradiation sur le comportement du chlore 37 dans le graphite nucléaire : conséquences sur la mobilité du chlore 36 dans les graphites irradiés : Effects of the temperature and the irradiation on the behaviour of chlorine 37 in nuclear graphite : consequences on the mobility of chlorine 36 in irradiated graphites.” 2013. Web. 18 Jan 2021.

Vancouver:

Blondel A. Effets de la température et de l’irradiation sur le comportement du chlore 37 dans le graphite nucléaire : conséquences sur la mobilité du chlore 36 dans les graphites irradiés : Effects of the temperature and the irradiation on the behaviour of chlorine 37 in nuclear graphite : consequences on the mobility of chlorine 36 in irradiated graphites. [Internet] [Doctoral dissertation]. Université Claude Bernard – Lyon I; 2013. [cited 2021 Jan 18]. Available from: http://www.theses.fr/2013LYO10323.

Council of Science Editors:

Blondel A. Effets de la température et de l’irradiation sur le comportement du chlore 37 dans le graphite nucléaire : conséquences sur la mobilité du chlore 36 dans les graphites irradiés : Effects of the temperature and the irradiation on the behaviour of chlorine 37 in nuclear graphite : consequences on the mobility of chlorine 36 in irradiated graphites. [Doctoral Dissertation]. Université Claude Bernard – Lyon I; 2013. Available from: http://www.theses.fr/2013LYO10323

22. Vaudey, Claire-Émilie. Effets de la température et de la corrosion radiolytique sur le comportement du chlore dans le graphite nucléaire : conséquences pour le stockage des graphites irradiés des réacteurs UNGG : Temperature and radiolytic corrosion effects on the chlorine behaviour in nuclear graphite : consequences for the disposabl of irradiated graphite from UNGG reactors.

Degree: Docteur es, Physico-chimie, 2010, Université Claude Bernard – Lyon I

Ce travail se situe dans le cadre des études sur la gestion des déchets graphites des centrales nucléaires Uranium Naturel Graphite Gaz (UNGG) de première… (more)

Subjects/Keywords: Chlore 36; Graphite nucléaire; Déchets nucléaires; Corrosion radiolytique; Speciation; Réacteurs UNGG; Chlorinee 36; Nuclear graphite; Nuclear wastes; Radiolytic corrosion; Speciation; UNGG reactors

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APA (6th Edition):

Vaudey, C. (2010). Effets de la température et de la corrosion radiolytique sur le comportement du chlore dans le graphite nucléaire : conséquences pour le stockage des graphites irradiés des réacteurs UNGG : Temperature and radiolytic corrosion effects on the chlorine behaviour in nuclear graphite : consequences for the disposabl of irradiated graphite from UNGG reactors. (Doctoral Dissertation). Université Claude Bernard – Lyon I. Retrieved from http://www.theses.fr/2010LYO10177

Chicago Manual of Style (16th Edition):

Vaudey, Claire-Émilie. “Effets de la température et de la corrosion radiolytique sur le comportement du chlore dans le graphite nucléaire : conséquences pour le stockage des graphites irradiés des réacteurs UNGG : Temperature and radiolytic corrosion effects on the chlorine behaviour in nuclear graphite : consequences for the disposabl of irradiated graphite from UNGG reactors.” 2010. Doctoral Dissertation, Université Claude Bernard – Lyon I. Accessed January 18, 2021. http://www.theses.fr/2010LYO10177.

MLA Handbook (7th Edition):

Vaudey, Claire-Émilie. “Effets de la température et de la corrosion radiolytique sur le comportement du chlore dans le graphite nucléaire : conséquences pour le stockage des graphites irradiés des réacteurs UNGG : Temperature and radiolytic corrosion effects on the chlorine behaviour in nuclear graphite : consequences for the disposabl of irradiated graphite from UNGG reactors.” 2010. Web. 18 Jan 2021.

Vancouver:

Vaudey C. Effets de la température et de la corrosion radiolytique sur le comportement du chlore dans le graphite nucléaire : conséquences pour le stockage des graphites irradiés des réacteurs UNGG : Temperature and radiolytic corrosion effects on the chlorine behaviour in nuclear graphite : consequences for the disposabl of irradiated graphite from UNGG reactors. [Internet] [Doctoral dissertation]. Université Claude Bernard – Lyon I; 2010. [cited 2021 Jan 18]. Available from: http://www.theses.fr/2010LYO10177.

Council of Science Editors:

Vaudey C. Effets de la température et de la corrosion radiolytique sur le comportement du chlore dans le graphite nucléaire : conséquences pour le stockage des graphites irradiés des réacteurs UNGG : Temperature and radiolytic corrosion effects on the chlorine behaviour in nuclear graphite : consequences for the disposabl of irradiated graphite from UNGG reactors. [Doctoral Dissertation]. Université Claude Bernard – Lyon I; 2010. Available from: http://www.theses.fr/2010LYO10177

23. Silbermann, Gwennaelle. Effets de la température et de l'irradiation sur le comportement du 14C et de son précurseur 14N dans le graphite nucléaire. Étude de la décontamination thermique du graphite en présence de vapeur d'eau : Temperature and irradiation effects on the behaviour of 14C and its precursor 14N in nuclear graphite. Study of a decontamination process using steam reforming.

Degree: Docteur es, Physico-chimie des matériaux, 2013, Université Claude Bernard – Lyon I

Le démantèlement des réacteurs Uranium Naturel Graphite Gaz génèrera en France environ 23 000 tonnes de déchets radioactifs graphités. La gestion appropriée de ces déchets… (more)

Subjects/Keywords: Carbone 14; Graphite nucléaire; Réacteur UNGG; Démantèlement; Déchets nucléaires; Corrosion radiolytique; Décontamination; Carbon 14; Nuclear graphite; UNGG reactors; Dismantling; Nuclear wastes; Radiolytic; Corrosion; 530

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APA (6th Edition):

Silbermann, G. (2013). Effets de la température et de l'irradiation sur le comportement du 14C et de son précurseur 14N dans le graphite nucléaire. Étude de la décontamination thermique du graphite en présence de vapeur d'eau : Temperature and irradiation effects on the behaviour of 14C and its precursor 14N in nuclear graphite. Study of a decontamination process using steam reforming. (Doctoral Dissertation). Université Claude Bernard – Lyon I. Retrieved from http://www.theses.fr/2013LYO10168

Chicago Manual of Style (16th Edition):

Silbermann, Gwennaelle. “Effets de la température et de l'irradiation sur le comportement du 14C et de son précurseur 14N dans le graphite nucléaire. Étude de la décontamination thermique du graphite en présence de vapeur d'eau : Temperature and irradiation effects on the behaviour of 14C and its precursor 14N in nuclear graphite. Study of a decontamination process using steam reforming.” 2013. Doctoral Dissertation, Université Claude Bernard – Lyon I. Accessed January 18, 2021. http://www.theses.fr/2013LYO10168.

MLA Handbook (7th Edition):

Silbermann, Gwennaelle. “Effets de la température et de l'irradiation sur le comportement du 14C et de son précurseur 14N dans le graphite nucléaire. Étude de la décontamination thermique du graphite en présence de vapeur d'eau : Temperature and irradiation effects on the behaviour of 14C and its precursor 14N in nuclear graphite. Study of a decontamination process using steam reforming.” 2013. Web. 18 Jan 2021.

Vancouver:

Silbermann G. Effets de la température et de l'irradiation sur le comportement du 14C et de son précurseur 14N dans le graphite nucléaire. Étude de la décontamination thermique du graphite en présence de vapeur d'eau : Temperature and irradiation effects on the behaviour of 14C and its precursor 14N in nuclear graphite. Study of a decontamination process using steam reforming. [Internet] [Doctoral dissertation]. Université Claude Bernard – Lyon I; 2013. [cited 2021 Jan 18]. Available from: http://www.theses.fr/2013LYO10168.

Council of Science Editors:

Silbermann G. Effets de la température et de l'irradiation sur le comportement du 14C et de son précurseur 14N dans le graphite nucléaire. Étude de la décontamination thermique du graphite en présence de vapeur d'eau : Temperature and irradiation effects on the behaviour of 14C and its precursor 14N in nuclear graphite. Study of a decontamination process using steam reforming. [Doctoral Dissertation]. Université Claude Bernard – Lyon I; 2013. Available from: http://www.theses.fr/2013LYO10168


Texas A&M University

24. Rauch, Eric B. Development of a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities.

Degree: MS, Nuclear Engineering, 2010, Texas A&M University

 Small graphite-moderated and gas-cooled reactors have been around since the beginning of the atomic age. Though their existence in the past has been associated with… (more)

Subjects/Keywords: graphite moderated reactor; nuclear safeguards; DPRK

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APA (6th Edition):

Rauch, E. B. (2010). Development of a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2009-05-739

Chicago Manual of Style (16th Edition):

Rauch, Eric B. “Development of a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities.” 2010. Masters Thesis, Texas A&M University. Accessed January 18, 2021. http://hdl.handle.net/1969.1/ETD-TAMU-2009-05-739.

MLA Handbook (7th Edition):

Rauch, Eric B. “Development of a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities.” 2010. Web. 18 Jan 2021.

Vancouver:

Rauch EB. Development of a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities. [Internet] [Masters thesis]. Texas A&M University; 2010. [cited 2021 Jan 18]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-05-739.

Council of Science Editors:

Rauch EB. Development of a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities. [Masters Thesis]. Texas A&M University; 2010. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2009-05-739


University of Manchester

25. Crump, Timothy. Modelling dynamic cracking of graphite.

Degree: 2017, University of Manchester

 Advances in dynamic fracture modelling have become more frequent due to increases in computer speed, meaning that its application to industrial problems has become viable.… (more)

Subjects/Keywords: graphite; dynamic fracture; XFEM; Cohesive zone; Nuclear; XCZM; Structural integrity; meso; Prompt Secondary Cracking; AGR

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APA (6th Edition):

Crump, T. (2017). Modelling dynamic cracking of graphite. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:312603

Chicago Manual of Style (16th Edition):

Crump, Timothy. “Modelling dynamic cracking of graphite.” 2017. Doctoral Dissertation, University of Manchester. Accessed January 18, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:312603.

MLA Handbook (7th Edition):

Crump, Timothy. “Modelling dynamic cracking of graphite.” 2017. Web. 18 Jan 2021.

Vancouver:

Crump T. Modelling dynamic cracking of graphite. [Internet] [Doctoral dissertation]. University of Manchester; 2017. [cited 2021 Jan 18]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:312603.

Council of Science Editors:

Crump T. Modelling dynamic cracking of graphite. [Doctoral Dissertation]. University of Manchester; 2017. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:312603


University of Missouri – Columbia

26. Lee, Yoonjo J., 1983-. Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios: Oxidation of nuclear- and matrix-grade graphite for Very High Temperature Reactor air ingress accident scenarios.

Degree: 2016, University of Missouri – Columbia

 One of the most severe accidents anticipated for the Very High Temperature Reactor (VHTR) is an air ingress accident caused by a pipe break, where… (more)

Subjects/Keywords: Nuclear reactors  – Safety measures  – Research; Graphite  – Thermal properties; Oxidation; Materials at high temperatures  – Testing.

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APA (6th Edition):

Lee, Yoonjo J., 1. (2016). Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios: Oxidation of nuclear- and matrix-grade graphite for Very High Temperature Reactor air ingress accident scenarios. (Thesis). University of Missouri – Columbia. Retrieved from https://doi.org/10.32469/10355/59845

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Lee, Yoonjo J., 1983-. “Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios: Oxidation of nuclear- and matrix-grade graphite for Very High Temperature Reactor air ingress accident scenarios.” 2016. Thesis, University of Missouri – Columbia. Accessed January 18, 2021. https://doi.org/10.32469/10355/59845.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Lee, Yoonjo J., 1983-. “Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios: Oxidation of nuclear- and matrix-grade graphite for Very High Temperature Reactor air ingress accident scenarios.” 2016. Web. 18 Jan 2021.

Vancouver:

Lee, Yoonjo J. 1. Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios: Oxidation of nuclear- and matrix-grade graphite for Very High Temperature Reactor air ingress accident scenarios. [Internet] [Thesis]. University of Missouri – Columbia; 2016. [cited 2021 Jan 18]. Available from: https://doi.org/10.32469/10355/59845.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Lee, Yoonjo J. 1. Oxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarios: Oxidation of nuclear- and matrix-grade graphite for Very High Temperature Reactor air ingress accident scenarios. [Thesis]. University of Missouri – Columbia; 2016. Available from: https://doi.org/10.32469/10355/59845

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of Southern California

27. White, Kevin Spencer. SQUID-based CW NMR system for measuring the magnetization of ³He films.

Degree: MS, Physics, 2012, University of Southern California

 This thesis describes the design and construction of a SQUID-based CW NMR system together with its application in a study of the two dimensional magnetism… (more)

Subjects/Keywords: helium; low-temperature; magnetization; ferromagnetism; quantum; nuclear spin; graphite; two-dimensional; NMR; spectroscopy

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APA (6th Edition):

White, K. S. (2012). SQUID-based CW NMR system for measuring the magnetization of ³He films. (Masters Thesis). University of Southern California. Retrieved from http://digitallibrary.usc.edu/cdm/compoundobject/collection/p15799coll3/id/120082/rec/6026

Chicago Manual of Style (16th Edition):

White, Kevin Spencer. “SQUID-based CW NMR system for measuring the magnetization of ³He films.” 2012. Masters Thesis, University of Southern California. Accessed January 18, 2021. http://digitallibrary.usc.edu/cdm/compoundobject/collection/p15799coll3/id/120082/rec/6026.

MLA Handbook (7th Edition):

White, Kevin Spencer. “SQUID-based CW NMR system for measuring the magnetization of ³He films.” 2012. Web. 18 Jan 2021.

Vancouver:

White KS. SQUID-based CW NMR system for measuring the magnetization of ³He films. [Internet] [Masters thesis]. University of Southern California; 2012. [cited 2021 Jan 18]. Available from: http://digitallibrary.usc.edu/cdm/compoundobject/collection/p15799coll3/id/120082/rec/6026.

Council of Science Editors:

White KS. SQUID-based CW NMR system for measuring the magnetization of ³He films. [Masters Thesis]. University of Southern California; 2012. Available from: http://digitallibrary.usc.edu/cdm/compoundobject/collection/p15799coll3/id/120082/rec/6026


University of Pretoria

28. Magampa, Philemon Podile. Properties of graphitic composites.

Degree: Chemistry, 2013, University of Pretoria

 The Pebble Bed Modular Reactor (PBMR) is a high temperature graphite-moderated nuclear reactor that uses helium as a coolant. The triple coated (TRISO) particles contain… (more)

Subjects/Keywords: Properties; Pebble Bed Modular Reactor (PBMR); Graphite-moderated nuclear reactor; TRISO; UCTD

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APA (6th Edition):

Magampa, P. P. (2013). Properties of graphitic composites. (Doctoral Dissertation). University of Pretoria. Retrieved from http://hdl.handle.net/2263/40244

Chicago Manual of Style (16th Edition):

Magampa, Philemon Podile. “Properties of graphitic composites.” 2013. Doctoral Dissertation, University of Pretoria. Accessed January 18, 2021. http://hdl.handle.net/2263/40244.

MLA Handbook (7th Edition):

Magampa, Philemon Podile. “Properties of graphitic composites.” 2013. Web. 18 Jan 2021.

Vancouver:

Magampa PP. Properties of graphitic composites. [Internet] [Doctoral dissertation]. University of Pretoria; 2013. [cited 2021 Jan 18]. Available from: http://hdl.handle.net/2263/40244.

Council of Science Editors:

Magampa PP. Properties of graphitic composites. [Doctoral Dissertation]. University of Pretoria; 2013. Available from: http://hdl.handle.net/2263/40244


University of Florida

29. Woods, Hugh Wilroy, 1941-. Theoretical and experimental investigation of the graphite phase diagram and graphite properties in the liquid core nuclear rocket pressure-temperature range.

Degree: 1969, University of Florida

Subjects/Keywords: Graphite  – Research; Graphite  – Thermodynamics; Nuclear reactors  – Materials; Nuclear Engineering Sciences thesis Ph. D; Graphite  – Research ( fast ); Nuclear reactors  – Materials ( fast )

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APA (6th Edition):

Woods, Hugh Wilroy, 1. (1969). Theoretical and experimental investigation of the graphite phase diagram and graphite properties in the liquid core nuclear rocket pressure-temperature range. (Thesis). University of Florida. Retrieved from https://ufdc.ufl.edu/AA00068270

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Woods, Hugh Wilroy, 1941-. “Theoretical and experimental investigation of the graphite phase diagram and graphite properties in the liquid core nuclear rocket pressure-temperature range.” 1969. Thesis, University of Florida. Accessed January 18, 2021. https://ufdc.ufl.edu/AA00068270.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Woods, Hugh Wilroy, 1941-. “Theoretical and experimental investigation of the graphite phase diagram and graphite properties in the liquid core nuclear rocket pressure-temperature range.” 1969. Web. 18 Jan 2021.

Vancouver:

Woods, Hugh Wilroy 1. Theoretical and experimental investigation of the graphite phase diagram and graphite properties in the liquid core nuclear rocket pressure-temperature range. [Internet] [Thesis]. University of Florida; 1969. [cited 2021 Jan 18]. Available from: https://ufdc.ufl.edu/AA00068270.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Woods, Hugh Wilroy 1. Theoretical and experimental investigation of the graphite phase diagram and graphite properties in the liquid core nuclear rocket pressure-temperature range. [Thesis]. University of Florida; 1969. Available from: https://ufdc.ufl.edu/AA00068270

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

30. Le Guillou, Maël. Migration du deutérium dans le graphite nucléaire : conséquences sur le comportement du tritium en réacteur UNGG et sur la décontamination des graphites irradiés : Deuterium migration in nuclear graphite : consequences for the behavior of tritium in Gas Cooled Reactors and for the decontamination of irradiated graphite waste.

Degree: Docteur es, Physique des matériaux, 2014, Université Claude Bernard – Lyon I

En France, 23 000 tonnes de graphites irradiés générés par le démantèlement des réacteurs nucléaires de première génération Uranium Naturel-Graphite-Gaz (UNGG) sont en attente d'une… (more)

Subjects/Keywords: UNGG; Démantèlement; Déchets radioactifs; Graphite; Tritium; Deutérium; Traitements thermiques; Inventaire radiologique; GCR; Dismantling; Nuclear waste; Graphite; Tritium; Deuterium; Heat treatments; Radiological inventory; 539.7

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APA (6th Edition):

Le Guillou, M. (2014). Migration du deutérium dans le graphite nucléaire : conséquences sur le comportement du tritium en réacteur UNGG et sur la décontamination des graphites irradiés : Deuterium migration in nuclear graphite : consequences for the behavior of tritium in Gas Cooled Reactors and for the decontamination of irradiated graphite waste. (Doctoral Dissertation). Université Claude Bernard – Lyon I. Retrieved from http://www.theses.fr/2014LYO10227

Chicago Manual of Style (16th Edition):

Le Guillou, Maël. “Migration du deutérium dans le graphite nucléaire : conséquences sur le comportement du tritium en réacteur UNGG et sur la décontamination des graphites irradiés : Deuterium migration in nuclear graphite : consequences for the behavior of tritium in Gas Cooled Reactors and for the decontamination of irradiated graphite waste.” 2014. Doctoral Dissertation, Université Claude Bernard – Lyon I. Accessed January 18, 2021. http://www.theses.fr/2014LYO10227.

MLA Handbook (7th Edition):

Le Guillou, Maël. “Migration du deutérium dans le graphite nucléaire : conséquences sur le comportement du tritium en réacteur UNGG et sur la décontamination des graphites irradiés : Deuterium migration in nuclear graphite : consequences for the behavior of tritium in Gas Cooled Reactors and for the decontamination of irradiated graphite waste.” 2014. Web. 18 Jan 2021.

Vancouver:

Le Guillou M. Migration du deutérium dans le graphite nucléaire : conséquences sur le comportement du tritium en réacteur UNGG et sur la décontamination des graphites irradiés : Deuterium migration in nuclear graphite : consequences for the behavior of tritium in Gas Cooled Reactors and for the decontamination of irradiated graphite waste. [Internet] [Doctoral dissertation]. Université Claude Bernard – Lyon I; 2014. [cited 2021 Jan 18]. Available from: http://www.theses.fr/2014LYO10227.

Council of Science Editors:

Le Guillou M. Migration du deutérium dans le graphite nucléaire : conséquences sur le comportement du tritium en réacteur UNGG et sur la décontamination des graphites irradiés : Deuterium migration in nuclear graphite : consequences for the behavior of tritium in Gas Cooled Reactors and for the decontamination of irradiated graphite waste. [Doctoral Dissertation]. Université Claude Bernard – Lyon I; 2014. Available from: http://www.theses.fr/2014LYO10227

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