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You searched for subject:(Irradiated oxide). Showing records 1 – 4 of 4 total matches.

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University of California – Berkeley

1. Bailey, Nathan. Atom probe tomographic analysis of high dose oxide-dispersion strengthened steel (alloy MA957) at selected irradiation conditions.

Degree: Nuclear Engineering, 2016, University of California – Berkeley

 In an effort to understand the effect of high dose neutron irradiation on fast reactor cladding candidate materials, oxide-dispersion strengthened (ODS) alloy MA957 was irradiated(more)

Subjects/Keywords: Nuclear engineering; Materials Science; Nanoscience; Atom Probe Tomography; Cluster Analysis; Neutron Irradiated Materials; Oxide-dispersion Strengthened Steel

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APA (6th Edition):

Bailey, N. (2016). Atom probe tomographic analysis of high dose oxide-dispersion strengthened steel (alloy MA957) at selected irradiation conditions. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/61h8k99k

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):

Bailey, Nathan. “Atom probe tomographic analysis of high dose oxide-dispersion strengthened steel (alloy MA957) at selected irradiation conditions.” 2016. Thesis, University of California – Berkeley. Accessed November 27, 2020. http://www.escholarship.org/uc/item/61h8k99k.

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

MLA Handbook (7th Edition):

Bailey, Nathan. “Atom probe tomographic analysis of high dose oxide-dispersion strengthened steel (alloy MA957) at selected irradiation conditions.” 2016. Web. 27 Nov 2020.

Vancouver:

Bailey N. Atom probe tomographic analysis of high dose oxide-dispersion strengthened steel (alloy MA957) at selected irradiation conditions. [Internet] [Thesis]. University of California – Berkeley; 2016. [cited 2020 Nov 27]. Available from: http://www.escholarship.org/uc/item/61h8k99k.

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

Council of Science Editors:

Bailey N. Atom probe tomographic analysis of high dose oxide-dispersion strengthened steel (alloy MA957) at selected irradiation conditions. [Thesis]. University of California – Berkeley; 2016. Available from: http://www.escholarship.org/uc/item/61h8k99k

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

2. Peyrillous, Marlène. Analyse du carbone 14, de l’iode 129 et du chlore 36 dans le combustible nucléaire irradié : Analysis of 14 carbon, 129 iodine and 36 chlorine in spent nuclear fuel.

Degree: Docteur es, Chimie, 2015, Université Claude Bernard – Lyon I

Le déploiement des futurs réacteurs à neutrons rapides, dits de Génération IV, est porteur d'améliorations prometteuses sur le plan de l'utilisation des matières premières et… (more)

Subjects/Keywords: Carbone 14; Chlore 36; Iode 129; Oxyde irradié; Chromatographie ionique; Scintillation solide; 14 carbon; 36 chlorine; 129 iodine; Irradiated oxide; Ion chromatography; Solid scintillation; 543

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APA (6th Edition):

Peyrillous, M. (2015). Analyse du carbone 14, de l’iode 129 et du chlore 36 dans le combustible nucléaire irradié : Analysis of 14 carbon, 129 iodine and 36 chlorine in spent nuclear fuel. (Doctoral Dissertation). Université Claude Bernard – Lyon I. Retrieved from http://www.theses.fr/2015LYO10218

Chicago Manual of Style (16th Edition):

Peyrillous, Marlène. “Analyse du carbone 14, de l’iode 129 et du chlore 36 dans le combustible nucléaire irradié : Analysis of 14 carbon, 129 iodine and 36 chlorine in spent nuclear fuel.” 2015. Doctoral Dissertation, Université Claude Bernard – Lyon I. Accessed November 27, 2020. http://www.theses.fr/2015LYO10218.

MLA Handbook (7th Edition):

Peyrillous, Marlène. “Analyse du carbone 14, de l’iode 129 et du chlore 36 dans le combustible nucléaire irradié : Analysis of 14 carbon, 129 iodine and 36 chlorine in spent nuclear fuel.” 2015. Web. 27 Nov 2020.

Vancouver:

Peyrillous M. Analyse du carbone 14, de l’iode 129 et du chlore 36 dans le combustible nucléaire irradié : Analysis of 14 carbon, 129 iodine and 36 chlorine in spent nuclear fuel. [Internet] [Doctoral dissertation]. Université Claude Bernard – Lyon I; 2015. [cited 2020 Nov 27]. Available from: http://www.theses.fr/2015LYO10218.

Council of Science Editors:

Peyrillous M. Analyse du carbone 14, de l’iode 129 et du chlore 36 dans le combustible nucléaire irradié : Analysis of 14 carbon, 129 iodine and 36 chlorine in spent nuclear fuel. [Doctoral Dissertation]. Université Claude Bernard – Lyon I; 2015. Available from: http://www.theses.fr/2015LYO10218


Penn State University

3. Ensor, Brendan Melvin. THE NATURE OF UNSTABLE OXIDE GROWTH IN ZIRCONIUM AND ZIRCONIUM ALLOYS.

Degree: 2016, Penn State University

 Zirconium alloys are commonly used as fuel claddings in nuclear reactors due in part to their superior corrosion resistance. The addition of small concentrations of… (more)

Subjects/Keywords: zirconium; zirconium alloy; fuel cladding; corrosion; synchrotron radiation; X-ray diffraction; XANES; neutron irradiated; Zircaloy-4; hydrogen; breakaway oxidation; strain; stress; plastic deformation; oxide growth; X-ray fluorescence; Raman spectroscopy; tetragonal fraction; grain size

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APA (6th Edition):

Ensor, B. M. (2016). THE NATURE OF UNSTABLE OXIDE GROWTH IN ZIRCONIUM AND ZIRCONIUM ALLOYS. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/13426bme133

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):

Ensor, Brendan Melvin. “THE NATURE OF UNSTABLE OXIDE GROWTH IN ZIRCONIUM AND ZIRCONIUM ALLOYS.” 2016. Thesis, Penn State University. Accessed November 27, 2020. https://submit-etda.libraries.psu.edu/catalog/13426bme133.

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

MLA Handbook (7th Edition):

Ensor, Brendan Melvin. “THE NATURE OF UNSTABLE OXIDE GROWTH IN ZIRCONIUM AND ZIRCONIUM ALLOYS.” 2016. Web. 27 Nov 2020.

Vancouver:

Ensor BM. THE NATURE OF UNSTABLE OXIDE GROWTH IN ZIRCONIUM AND ZIRCONIUM ALLOYS. [Internet] [Thesis]. Penn State University; 2016. [cited 2020 Nov 27]. Available from: https://submit-etda.libraries.psu.edu/catalog/13426bme133.

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

Council of Science Editors:

Ensor BM. THE NATURE OF UNSTABLE OXIDE GROWTH IN ZIRCONIUM AND ZIRCONIUM ALLOYS. [Thesis]. Penn State University; 2016. Available from: https://submit-etda.libraries.psu.edu/catalog/13426bme133

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


University of Oxford

4. Jones, Christopher A. A micromechanical investigation of proton irradiated oxide dispersion strengthened steels.

Degree: PhD, 2016, University of Oxford

 This thesis was most concerned with the mechanical response to irradiation of two in-house produced oxide dispersion strengthened (ODS) steels and two non-ODS coun- terparts.… (more)

Subjects/Keywords: 620.1; Micromechanical examination of irradiated layers; Micromecanical testing methods; Lengthscale-dependent crystal plasticity; Micromechanical size effect; Four-point flexure testing; Micromechanical size efffect; Microcantilever; ODS steels; Microcantilever size effect; Proton irradiation; Oxide dispersion strengthened steels; Proton irradiatied layer; Crystal plasticity; Nanoindentation; Four-point bend testing

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APA (6th Edition):

Jones, C. A. (2016). A micromechanical investigation of proton irradiated oxide dispersion strengthened steels. (Doctoral Dissertation). University of Oxford. Retrieved from http://ora.ox.ac.uk/objects/uuid:fadd9abf-b5d0-4ea1-9d86-50628ec0476a ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.748672

Chicago Manual of Style (16th Edition):

Jones, Christopher A. “A micromechanical investigation of proton irradiated oxide dispersion strengthened steels.” 2016. Doctoral Dissertation, University of Oxford. Accessed November 27, 2020. http://ora.ox.ac.uk/objects/uuid:fadd9abf-b5d0-4ea1-9d86-50628ec0476a ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.748672.

MLA Handbook (7th Edition):

Jones, Christopher A. “A micromechanical investigation of proton irradiated oxide dispersion strengthened steels.” 2016. Web. 27 Nov 2020.

Vancouver:

Jones CA. A micromechanical investigation of proton irradiated oxide dispersion strengthened steels. [Internet] [Doctoral dissertation]. University of Oxford; 2016. [cited 2020 Nov 27]. Available from: http://ora.ox.ac.uk/objects/uuid:fadd9abf-b5d0-4ea1-9d86-50628ec0476a ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.748672.

Council of Science Editors:

Jones CA. A micromechanical investigation of proton irradiated oxide dispersion strengthened steels. [Doctoral Dissertation]. University of Oxford; 2016. Available from: http://ora.ox.ac.uk/objects/uuid:fadd9abf-b5d0-4ea1-9d86-50628ec0476a ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.748672

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