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You searched for subject:(BWR). Showing records 1 – 30 of 54 total matches.

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Penn State University

1. Walls, Robert Allen. BOILING WATER REACTOR TRANSIENT INSTABILITY STUDIES OF RINGHALS 1 REACTOR USING TRACE COUPLED WITH PARCS.

Degree: MS, Nuclear Engineering, 2009, Penn State University

 Reactor plant design often incorporates data and insight ascertained from computer code simulations of plant dynamics and reactor core behavior. Increasing utilization of data gathered… (more)

Subjects/Keywords: BWR Instabilities; Ringhals; TRACE

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APA (6th Edition):

Walls, R. A. (2009). BOILING WATER REACTOR TRANSIENT INSTABILITY STUDIES OF RINGHALS 1 REACTOR USING TRACE COUPLED WITH PARCS. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/10194

Chicago Manual of Style (16th Edition):

Walls, Robert Allen. “BOILING WATER REACTOR TRANSIENT INSTABILITY STUDIES OF RINGHALS 1 REACTOR USING TRACE COUPLED WITH PARCS.” 2009. Masters Thesis, Penn State University. Accessed March 20, 2019. https://etda.libraries.psu.edu/catalog/10194.

MLA Handbook (7th Edition):

Walls, Robert Allen. “BOILING WATER REACTOR TRANSIENT INSTABILITY STUDIES OF RINGHALS 1 REACTOR USING TRACE COUPLED WITH PARCS.” 2009. Web. 20 Mar 2019.

Vancouver:

Walls RA. BOILING WATER REACTOR TRANSIENT INSTABILITY STUDIES OF RINGHALS 1 REACTOR USING TRACE COUPLED WITH PARCS. [Internet] [Masters thesis]. Penn State University; 2009. [cited 2019 Mar 20]. Available from: https://etda.libraries.psu.edu/catalog/10194.

Council of Science Editors:

Walls RA. BOILING WATER REACTOR TRANSIENT INSTABILITY STUDIES OF RINGHALS 1 REACTOR USING TRACE COUPLED WITH PARCS. [Masters Thesis]. Penn State University; 2009. Available from: https://etda.libraries.psu.edu/catalog/10194


Universitat Politècnica de València

2. MELARA SAN ROMÁN, JOSÉ. PREDICTIVE METHODS FOR STABILITY MARGIN IN BWR .

Degree: 2016, Universitat Politècnica de València

 [EN] Power and flow oscillations in a BWR are very undesirable. One of the major concerns is to ensure, during power oscillations, compliance with GDC… (more)

Subjects/Keywords: Stability; BWR; Decay Ratio; LAPUR

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APA (6th Edition):

MELARA SAN ROMÁN, J. (2016). PREDICTIVE METHODS FOR STABILITY MARGIN IN BWR . (Doctoral Dissertation). Universitat Politècnica de València. Retrieved from http://hdl.handle.net/10251/61307

Chicago Manual of Style (16th Edition):

MELARA SAN ROMÁN, JOSÉ. “PREDICTIVE METHODS FOR STABILITY MARGIN IN BWR .” 2016. Doctoral Dissertation, Universitat Politècnica de València. Accessed March 20, 2019. http://hdl.handle.net/10251/61307.

MLA Handbook (7th Edition):

MELARA SAN ROMÁN, JOSÉ. “PREDICTIVE METHODS FOR STABILITY MARGIN IN BWR .” 2016. Web. 20 Mar 2019.

Vancouver:

MELARA SAN ROMÁN J. PREDICTIVE METHODS FOR STABILITY MARGIN IN BWR . [Internet] [Doctoral dissertation]. Universitat Politècnica de València; 2016. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/10251/61307.

Council of Science Editors:

MELARA SAN ROMÁN J. PREDICTIVE METHODS FOR STABILITY MARGIN IN BWR . [Doctoral Dissertation]. Universitat Politècnica de València; 2016. Available from: http://hdl.handle.net/10251/61307

3. Persson, Olle. Modeling of the process system in a boiling water reactor.

Degree: 2012, Chalmers University of Technology

 The subject of this master thesis is modeling of the process system in a boiling water reactor, and in particular Ringhals 1. The modeling is… (more)

Subjects/Keywords: Modeling; Boiling water reactor; BWR; Ringhals; Dymola

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APA (6th Edition):

Persson, O. (2012). Modeling of the process system in a boiling water reactor. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/162617-modeling-of-the-process-system-in-a-boiling-water-reactor

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):

Persson, Olle. “Modeling of the process system in a boiling water reactor.” 2012. Thesis, Chalmers University of Technology. Accessed March 20, 2019. http://studentarbeten.chalmers.se/publication/162617-modeling-of-the-process-system-in-a-boiling-water-reactor.

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

MLA Handbook (7th Edition):

Persson, Olle. “Modeling of the process system in a boiling water reactor.” 2012. Web. 20 Mar 2019.

Vancouver:

Persson O. Modeling of the process system in a boiling water reactor. [Internet] [Thesis]. Chalmers University of Technology; 2012. [cited 2019 Mar 20]. Available from: http://studentarbeten.chalmers.se/publication/162617-modeling-of-the-process-system-in-a-boiling-water-reactor.

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

Council of Science Editors:

Persson O. Modeling of the process system in a boiling water reactor. [Thesis]. Chalmers University of Technology; 2012. Available from: http://studentarbeten.chalmers.se/publication/162617-modeling-of-the-process-system-in-a-boiling-water-reactor

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


Texas A&M University

4. Salpeter, Nathaniel. Development of Spatio-Temporal Wavelet Post Processing Techniques for Application to Thermal Hydraulic Experiments and Numerical Simulations.

Degree: 2012, Texas A&M University

 This work focuses on both high fidelity experimental and numerical thermal hydraulic studies and advanced frequency decomposition methods. The major contribution of this work is… (more)

Subjects/Keywords: Wavelet; decomposition; nuclear; PTV; CFD; BWR

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APA (6th Edition):

Salpeter, N. (2012). Development of Spatio-Temporal Wavelet Post Processing Techniques for Application to Thermal Hydraulic Experiments and Numerical Simulations. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10998

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):

Salpeter, Nathaniel. “Development of Spatio-Temporal Wavelet Post Processing Techniques for Application to Thermal Hydraulic Experiments and Numerical Simulations.” 2012. Thesis, Texas A&M University. Accessed March 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10998.

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

MLA Handbook (7th Edition):

Salpeter, Nathaniel. “Development of Spatio-Temporal Wavelet Post Processing Techniques for Application to Thermal Hydraulic Experiments and Numerical Simulations.” 2012. Web. 20 Mar 2019.

Vancouver:

Salpeter N. Development of Spatio-Temporal Wavelet Post Processing Techniques for Application to Thermal Hydraulic Experiments and Numerical Simulations. [Internet] [Thesis]. Texas A&M University; 2012. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10998.

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

Council of Science Editors:

Salpeter N. Development of Spatio-Temporal Wavelet Post Processing Techniques for Application to Thermal Hydraulic Experiments and Numerical Simulations. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-05-10998

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


Uppsala University

5. Fridström, Richard. Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor.

Degree: Applied Nuclear Physics, 2010, Uppsala University

  In order to monitor a nuclear boiling water reactor fixed and movable detectors are used, such as the neutron sensitive LPRM (Local Power Range… (more)

Subjects/Keywords: TIP; BWR; gamma; detector; MCNP; POLCA

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APA (6th Edition):

Fridström, R. (2010). Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-126969

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):

Fridström, Richard. “Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor.” 2010. Thesis, Uppsala University. Accessed March 20, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-126969.

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

MLA Handbook (7th Edition):

Fridström, Richard. “Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor.” 2010. Web. 20 Mar 2019.

Vancouver:

Fridström R. Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor. [Internet] [Thesis]. Uppsala University; 2010. [cited 2019 Mar 20]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-126969.

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

Council of Science Editors:

Fridström R. Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor. [Thesis]. Uppsala University; 2010. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-126969

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

6. Azadrad, Alborz. Statistical analysis of plant data for revision of operating rules minimizing risk of PCI failure in BWRs.

Degree: 2013, Chalmers University of Technology

 Nuclear power reactors are responsible for producing electricity; the electricity comes from a generator, driven by turbines that receive their power from expanding steam forcing… (more)

Subjects/Keywords: PCI; Westinghouse; Statistics; Nuclear; Pellet; BWR; Liner; Probability; Failure; Cladding

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APA (6th Edition):

Azadrad, A. (2013). Statistical analysis of plant data for revision of operating rules minimizing risk of PCI failure in BWRs. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/187035-statistical-analysis-of-plant-data-for-revision-of-operating-rules-minimizing-risk-of-pci-failure-in

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):

Azadrad, Alborz. “Statistical analysis of plant data for revision of operating rules minimizing risk of PCI failure in BWRs.” 2013. Thesis, Chalmers University of Technology. Accessed March 20, 2019. http://studentarbeten.chalmers.se/publication/187035-statistical-analysis-of-plant-data-for-revision-of-operating-rules-minimizing-risk-of-pci-failure-in.

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

MLA Handbook (7th Edition):

Azadrad, Alborz. “Statistical analysis of plant data for revision of operating rules minimizing risk of PCI failure in BWRs.” 2013. Web. 20 Mar 2019.

Vancouver:

Azadrad A. Statistical analysis of plant data for revision of operating rules minimizing risk of PCI failure in BWRs. [Internet] [Thesis]. Chalmers University of Technology; 2013. [cited 2019 Mar 20]. Available from: http://studentarbeten.chalmers.se/publication/187035-statistical-analysis-of-plant-data-for-revision-of-operating-rules-minimizing-risk-of-pci-failure-in.

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

Council of Science Editors:

Azadrad A. Statistical analysis of plant data for revision of operating rules minimizing risk of PCI failure in BWRs. [Thesis]. Chalmers University of Technology; 2013. Available from: http://studentarbeten.chalmers.se/publication/187035-statistical-analysis-of-plant-data-for-revision-of-operating-rules-minimizing-risk-of-pci-failure-in

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

7. Herbst, Matthias G. J. Effect of chloride on environmentally assisted cracking of low alloy steels in oxygenated high temperature water.

Degree: PhD, 2014, Liverpool John Moores University

 The aim of this thesis was to derive a better understanding with regard to the effects of chloride on the general corrosion behaviour of low-alloy… (more)

Subjects/Keywords: 669; Low Alloy Steel, Chloride, High Temperature Water, Anionic Impurities, BWR

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APA (6th Edition):

Herbst, M. G. J. (2014). Effect of chloride on environmentally assisted cracking of low alloy steels in oxygenated high temperature water. (Doctoral Dissertation). Liverpool John Moores University. Retrieved from http://researchonline.ljmu.ac.uk/4569/ ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.594280

Chicago Manual of Style (16th Edition):

Herbst, Matthias G J. “Effect of chloride on environmentally assisted cracking of low alloy steels in oxygenated high temperature water.” 2014. Doctoral Dissertation, Liverpool John Moores University. Accessed March 20, 2019. http://researchonline.ljmu.ac.uk/4569/ ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.594280.

MLA Handbook (7th Edition):

Herbst, Matthias G J. “Effect of chloride on environmentally assisted cracking of low alloy steels in oxygenated high temperature water.” 2014. Web. 20 Mar 2019.

Vancouver:

Herbst MGJ. Effect of chloride on environmentally assisted cracking of low alloy steels in oxygenated high temperature water. [Internet] [Doctoral dissertation]. Liverpool John Moores University; 2014. [cited 2019 Mar 20]. Available from: http://researchonline.ljmu.ac.uk/4569/ ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.594280.

Council of Science Editors:

Herbst MGJ. Effect of chloride on environmentally assisted cracking of low alloy steels in oxygenated high temperature water. [Doctoral Dissertation]. Liverpool John Moores University; 2014. Available from: http://researchonline.ljmu.ac.uk/4569/ ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.594280


Penn State University

8. Puente Espel, Federico. HIGH ACCURACY MODELING FOR ADVANCED NUCLEAR REACTOR CORE DESIGNS USING MONTE CARLO BASED COUPLED CALCULATIONS.

Degree: PhD, Nuclear Engineering, 2010, Penn State University

 The main objective of this PhD research is to develop a high accuracy modeling tool using a Monte Carlo based coupled system. The presented research… (more)

Subjects/Keywords: MCNP5; COBRA-TF; NJOY; NEM; Coupled Calculations; BWR

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APA (6th Edition):

Puente Espel, F. (2010). HIGH ACCURACY MODELING FOR ADVANCED NUCLEAR REACTOR CORE DESIGNS USING MONTE CARLO BASED COUPLED CALCULATIONS. (Doctoral Dissertation). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/10913

Chicago Manual of Style (16th Edition):

Puente Espel, Federico. “HIGH ACCURACY MODELING FOR ADVANCED NUCLEAR REACTOR CORE DESIGNS USING MONTE CARLO BASED COUPLED CALCULATIONS.” 2010. Doctoral Dissertation, Penn State University. Accessed March 20, 2019. https://etda.libraries.psu.edu/catalog/10913.

MLA Handbook (7th Edition):

Puente Espel, Federico. “HIGH ACCURACY MODELING FOR ADVANCED NUCLEAR REACTOR CORE DESIGNS USING MONTE CARLO BASED COUPLED CALCULATIONS.” 2010. Web. 20 Mar 2019.

Vancouver:

Puente Espel F. HIGH ACCURACY MODELING FOR ADVANCED NUCLEAR REACTOR CORE DESIGNS USING MONTE CARLO BASED COUPLED CALCULATIONS. [Internet] [Doctoral dissertation]. Penn State University; 2010. [cited 2019 Mar 20]. Available from: https://etda.libraries.psu.edu/catalog/10913.

Council of Science Editors:

Puente Espel F. HIGH ACCURACY MODELING FOR ADVANCED NUCLEAR REACTOR CORE DESIGNS USING MONTE CARLO BASED COUPLED CALCULATIONS. [Doctoral Dissertation]. Penn State University; 2010. Available from: https://etda.libraries.psu.edu/catalog/10913

9. 平川, 裕雅. 数値解析によるBWR上部プレナム内における音響共鳴現象評価(要旨).

Degree: 修士(環境学), 2017, The University of Tokyo / 東京大学

 In recent years, the power uprate of Boiling Water Reactors have been conducted at several power plants, but many problem has reported. Particularly, Quad Cities… (more)

Subjects/Keywords: BWR; acoustic analysis; Steam Dryer; Flow-Induced Acoustic Resonance

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APA (6th Edition):

平川, . (2017). 数値解析によるBWR上部プレナム内における音響共鳴現象評価(要旨). (Thesis). The University of Tokyo / 東京大学. Retrieved from http://hdl.handle.net/2261/37200

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):

平川, 裕雅. “数値解析によるBWR上部プレナム内における音響共鳴現象評価(要旨).” 2017. Thesis, The University of Tokyo / 東京大学. Accessed March 20, 2019. http://hdl.handle.net/2261/37200.

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

MLA Handbook (7th Edition):

平川, 裕雅. “数値解析によるBWR上部プレナム内における音響共鳴現象評価(要旨).” 2017. Web. 20 Mar 2019.

Vancouver:

平川 . 数値解析によるBWR上部プレナム内における音響共鳴現象評価(要旨). [Internet] [Thesis]. The University of Tokyo / 東京大学; 2017. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/2261/37200.

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

Council of Science Editors:

平川 . 数値解析によるBWR上部プレナム内における音響共鳴現象評価(要旨). [Thesis]. The University of Tokyo / 東京大学; 2017. Available from: http://hdl.handle.net/2261/37200

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

10. 関口, 秀樹. BWR状態方程式による異種分子間相互作用パラメータmijの再相関 : Correlation of the binary interaction parameters, mij for the systems containing a non-polar substance by the modified generalized BWR equation of state.

Degree: 2011, Hosei University / 法政大学

 Based on the relation suggested by Hudson and McCoubery, we proposed new mixing rules for the coefficients of the modified generalized BWR equation of state… (more)

Subjects/Keywords: modified generalized BWR equation of state; interaction parameter; VLE

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APA (6th Edition):

関口, . (2011). BWR状態方程式による異種分子間相互作用パラメータmijの再相関 : Correlation of the binary interaction parameters, mij for the systems containing a non-polar substance by the modified generalized BWR equation of state. (Thesis). Hosei University / 法政大学. Retrieved from http://hdl.handle.net/10114/6899

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):

関口, 秀樹. “BWR状態方程式による異種分子間相互作用パラメータmijの再相関 : Correlation of the binary interaction parameters, mij for the systems containing a non-polar substance by the modified generalized BWR equation of state.” 2011. Thesis, Hosei University / 法政大学. Accessed March 20, 2019. http://hdl.handle.net/10114/6899.

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

MLA Handbook (7th Edition):

関口, 秀樹. “BWR状態方程式による異種分子間相互作用パラメータmijの再相関 : Correlation of the binary interaction parameters, mij for the systems containing a non-polar substance by the modified generalized BWR equation of state.” 2011. Web. 20 Mar 2019.

Vancouver:

関口 . BWR状態方程式による異種分子間相互作用パラメータmijの再相関 : Correlation of the binary interaction parameters, mij for the systems containing a non-polar substance by the modified generalized BWR equation of state. [Internet] [Thesis]. Hosei University / 法政大学; 2011. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/10114/6899.

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

Council of Science Editors:

関口 . BWR状態方程式による異種分子間相互作用パラメータmijの再相関 : Correlation of the binary interaction parameters, mij for the systems containing a non-polar substance by the modified generalized BWR equation of state. [Thesis]. Hosei University / 法政大学; 2011. Available from: http://hdl.handle.net/10114/6899

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

11. 秋定, 諒亮. 成分ファミリー法によるBWR状態方程式における異種分子間相互作用パラメータの相関 : CORRELATION OF THE BINARY INTERACTION PARAMETER IN THE MODIFIED GENERALIZED BWR EQUATION OF STATE BY THE LAW OF CHEMICAL COMPONENT FAMILY .

Degree: 2013, Hosei University / 法政大学

 Based on the relation suggested by Hudson and McCoubrey, we wrote correlation equation of the binary interaction parameter. We found that the binary interaction parameter… (more)

Subjects/Keywords: modified generalized BWR equation of state; binary interaction parameter

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APA (6th Edition):

秋定, . (2013). 成分ファミリー法によるBWR状態方程式における異種分子間相互作用パラメータの相関 : CORRELATION OF THE BINARY INTERACTION PARAMETER IN THE MODIFIED GENERALIZED BWR EQUATION OF STATE BY THE LAW OF CHEMICAL COMPONENT FAMILY . (Thesis). Hosei University / 法政大学. Retrieved from http://hdl.handle.net/10114/8683

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):

秋定, 諒亮. “成分ファミリー法によるBWR状態方程式における異種分子間相互作用パラメータの相関 : CORRELATION OF THE BINARY INTERACTION PARAMETER IN THE MODIFIED GENERALIZED BWR EQUATION OF STATE BY THE LAW OF CHEMICAL COMPONENT FAMILY .” 2013. Thesis, Hosei University / 法政大学. Accessed March 20, 2019. http://hdl.handle.net/10114/8683.

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

MLA Handbook (7th Edition):

秋定, 諒亮. “成分ファミリー法によるBWR状態方程式における異種分子間相互作用パラメータの相関 : CORRELATION OF THE BINARY INTERACTION PARAMETER IN THE MODIFIED GENERALIZED BWR EQUATION OF STATE BY THE LAW OF CHEMICAL COMPONENT FAMILY .” 2013. Web. 20 Mar 2019.

Vancouver:

秋定 . 成分ファミリー法によるBWR状態方程式における異種分子間相互作用パラメータの相関 : CORRELATION OF THE BINARY INTERACTION PARAMETER IN THE MODIFIED GENERALIZED BWR EQUATION OF STATE BY THE LAW OF CHEMICAL COMPONENT FAMILY . [Internet] [Thesis]. Hosei University / 法政大学; 2013. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/10114/8683.

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

Council of Science Editors:

秋定 . 成分ファミリー法によるBWR状態方程式における異種分子間相互作用パラメータの相関 : CORRELATION OF THE BINARY INTERACTION PARAMETER IN THE MODIFIED GENERALIZED BWR EQUATION OF STATE BY THE LAW OF CHEMICAL COMPONENT FAMILY . [Thesis]. Hosei University / 法政大学; 2013. Available from: http://hdl.handle.net/10114/8683

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

12. Fritz, Malin. Control rod drop during hot zero power : RIA in BWR.

Degree: Applied Nuclear Physics, 2013, Uppsala University

  During operation of nuclear power reactors reactivity initiated accidents (RIA) can occur, such as a control rod drop. If this occurs, the reactivity increase… (more)

Subjects/Keywords: Control rod; RIA; BWR

…accidents. During operation of a boiling water reactor (BWR) control rods are used to… …group at Forsmark NPP. 10 2. BOILING WATER REACTOR A boiling water reactor (BWR)… …or hafnium that are prone to absorb neutrons. For a BWR; the control rod blades form a… …see figure 3. In a BWR the control rods are inserted from below by a mechanical drive… …reactivity addition in the reactor. Figure 6 – A typical start up for a BWR. Green line – control… 

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APA (6th Edition):

Fritz, M. (2013). Control rod drop during hot zero power : RIA in BWR. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-201890

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):

Fritz, Malin. “Control rod drop during hot zero power : RIA in BWR.” 2013. Thesis, Uppsala University. Accessed March 20, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-201890.

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

MLA Handbook (7th Edition):

Fritz, Malin. “Control rod drop during hot zero power : RIA in BWR.” 2013. Web. 20 Mar 2019.

Vancouver:

Fritz M. Control rod drop during hot zero power : RIA in BWR. [Internet] [Thesis]. Uppsala University; 2013. [cited 2019 Mar 20]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-201890.

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

Council of Science Editors:

Fritz M. Control rod drop during hot zero power : RIA in BWR. [Thesis]. Uppsala University; 2013. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-201890

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

13. Ohlsson, Daniel. Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2.

Degree: IT and Land Management, 2017, University of Gävle

  In the process of a boiling water reactor, high-levels of waste and radiation occur, where almost all the dose per person of the radiation… (more)

Subjects/Keywords: Boiling Water Reactor; BWR; Stellite; Forsmark; Cobalt; Cobalt-59; Kokvattenreaktor; BWR; Stellite; Forsmark; kobolt; kobolt-59; kobolt-60; korrosion; dosrat; strålning; Other Mechanical Engineering; Annan maskinteknik

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APA (6th Edition):

Ohlsson, D. (2017). Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2. (Thesis). University of Gävle. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-25130

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):

Ohlsson, Daniel. “Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2.” 2017. Thesis, University of Gävle. Accessed March 20, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-25130.

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

MLA Handbook (7th Edition):

Ohlsson, Daniel. “Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2.” 2017. Web. 20 Mar 2019.

Vancouver:

Ohlsson D. Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2. [Internet] [Thesis]. University of Gävle; 2017. [cited 2019 Mar 20]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-25130.

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

Council of Science Editors:

Ohlsson D. Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2. [Thesis]. University of Gävle; 2017. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-25130

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


University of Utah

14. Eklund, Matthew Deric. A new thermal hydraulics code coupled to agent for light water reactor analysis.

Degree: MSin Nuclear Engineering, Civil & Environmental Engineering, 2016, University of Utah

 A new numerical model for coupling a thermal hydraulics method based on the Drift Flux and Homogeneous Equilibrium Mixture (HEM) models, with a deterministic neutronics… (more)

Subjects/Keywords: AGENT; BWR; Drift flux model; Homogeneous Equilibrium Mixture (HEM) model; Method of Characteristics; PWR

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APA (6th Edition):

Eklund, M. D. (2016). A new thermal hydraulics code coupled to agent for light water reactor analysis. (Masters Thesis). University of Utah. Retrieved from http://content.lib.utah.edu/cdm/singleitem/collection/etd3/id/4097/rec/61

Chicago Manual of Style (16th Edition):

Eklund, Matthew Deric. “A new thermal hydraulics code coupled to agent for light water reactor analysis.” 2016. Masters Thesis, University of Utah. Accessed March 20, 2019. http://content.lib.utah.edu/cdm/singleitem/collection/etd3/id/4097/rec/61.

MLA Handbook (7th Edition):

Eklund, Matthew Deric. “A new thermal hydraulics code coupled to agent for light water reactor analysis.” 2016. Web. 20 Mar 2019.

Vancouver:

Eklund MD. A new thermal hydraulics code coupled to agent for light water reactor analysis. [Internet] [Masters thesis]. University of Utah; 2016. [cited 2019 Mar 20]. Available from: http://content.lib.utah.edu/cdm/singleitem/collection/etd3/id/4097/rec/61.

Council of Science Editors:

Eklund MD. A new thermal hydraulics code coupled to agent for light water reactor analysis. [Masters Thesis]. University of Utah; 2016. Available from: http://content.lib.utah.edu/cdm/singleitem/collection/etd3/id/4097/rec/61


Texas A&M University

15. Yancey, Kristina. Nationwide Used Fuel Inventory Analysis.

Degree: 2013, Texas A&M University

 The goal of this research was to develop a methodology to collect inventory estimates for the analysis and characterization of used fuel in the United… (more)

Subjects/Keywords: nuclear; energy; spent fuel; used fuel; nuclide inventories; PWR; BWR; applicability range

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APA (6th Edition):

Yancey, K. (2013). Nationwide Used Fuel Inventory Analysis. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/151866

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):

Yancey, Kristina. “Nationwide Used Fuel Inventory Analysis.” 2013. Thesis, Texas A&M University. Accessed March 20, 2019. http://hdl.handle.net/1969.1/151866.

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

MLA Handbook (7th Edition):

Yancey, Kristina. “Nationwide Used Fuel Inventory Analysis.” 2013. Web. 20 Mar 2019.

Vancouver:

Yancey K. Nationwide Used Fuel Inventory Analysis. [Internet] [Thesis]. Texas A&M University; 2013. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1969.1/151866.

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

Council of Science Editors:

Yancey K. Nationwide Used Fuel Inventory Analysis. [Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/151866

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


Texas A&M University

16. Fullerton, Christopher Todd. Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing.

Degree: MS, Nuclear Engineering, 2017, Texas A&M University

 In the event that a nuclear core cooling pipe ruptures, a loss of coolant accident (LOCA) scenario begins. Precipitates from dissolved ions can form and… (more)

Subjects/Keywords: GSI-191; Alumina; Corrosion; Sodium Tetraborate (NaTB); Loss of Coolant Accident (LOCA); PWR; BWR

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APA (6th Edition):

Fullerton, C. T. (2017). Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/165685

Chicago Manual of Style (16th Edition):

Fullerton, Christopher Todd. “Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing.” 2017. Masters Thesis, Texas A&M University. Accessed March 20, 2019. http://hdl.handle.net/1969.1/165685.

MLA Handbook (7th Edition):

Fullerton, Christopher Todd. “Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing.” 2017. Web. 20 Mar 2019.

Vancouver:

Fullerton CT. Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing. [Internet] [Masters thesis]. Texas A&M University; 2017. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1969.1/165685.

Council of Science Editors:

Fullerton CT. Characterization of Aluminum Corrosion Precipitates in Support of GSI-191 Head Loss Testing. [Masters Thesis]. Texas A&M University; 2017. Available from: http://hdl.handle.net/1969.1/165685

17. Ahnesjö, Magnus. Tomographic reconstruction of subchannel void measurements of nuclear fuel geometries.

Degree: Applied Nuclear Physics, 2015, Uppsala University

  The Westinghouse FRIGG loop in Västerås, Sweden, has been used to study the distribution of steam in the coolant flow of nuclear fuel elements,… (more)

Subjects/Keywords: tomography; void; nucler power; bwr

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APA (6th Edition):

Ahnesjö, M. (2015). Tomographic reconstruction of subchannel void measurements of nuclear fuel geometries. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-246288

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):

Ahnesjö, Magnus. “Tomographic reconstruction of subchannel void measurements of nuclear fuel geometries.” 2015. Thesis, Uppsala University. Accessed March 20, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-246288.

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

MLA Handbook (7th Edition):

Ahnesjö, Magnus. “Tomographic reconstruction of subchannel void measurements of nuclear fuel geometries.” 2015. Web. 20 Mar 2019.

Vancouver:

Ahnesjö M. Tomographic reconstruction of subchannel void measurements of nuclear fuel geometries. [Internet] [Thesis]. Uppsala University; 2015. [cited 2019 Mar 20]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-246288.

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

Council of Science Editors:

Ahnesjö M. Tomographic reconstruction of subchannel void measurements of nuclear fuel geometries. [Thesis]. Uppsala University; 2015. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-246288

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


Penn State University

18. Akdeniz, Bedirhan. IMPROVED NEUTRON KINETICS FOR COUPLED THREE-DIMENSIONAL BOILING WATER REACTOR ANALYSIS.

Degree: PhD, Nuclear Engineering, 2007, Penn State University

 The need for a more accurate method of modeling cross section variations for off-nominal core conditions is becoming an important issue with the increased use… (more)

Subjects/Keywords: Neutron Kinetics; Delayed Neutron; Importance Factor; Parameterization Technique; BWR

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APA (6th Edition):

Akdeniz, B. (2007). IMPROVED NEUTRON KINETICS FOR COUPLED THREE-DIMENSIONAL BOILING WATER REACTOR ANALYSIS. (Doctoral Dissertation). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/7904

Chicago Manual of Style (16th Edition):

Akdeniz, Bedirhan. “IMPROVED NEUTRON KINETICS FOR COUPLED THREE-DIMENSIONAL BOILING WATER REACTOR ANALYSIS.” 2007. Doctoral Dissertation, Penn State University. Accessed March 20, 2019. https://etda.libraries.psu.edu/catalog/7904.

MLA Handbook (7th Edition):

Akdeniz, Bedirhan. “IMPROVED NEUTRON KINETICS FOR COUPLED THREE-DIMENSIONAL BOILING WATER REACTOR ANALYSIS.” 2007. Web. 20 Mar 2019.

Vancouver:

Akdeniz B. IMPROVED NEUTRON KINETICS FOR COUPLED THREE-DIMENSIONAL BOILING WATER REACTOR ANALYSIS. [Internet] [Doctoral dissertation]. Penn State University; 2007. [cited 2019 Mar 20]. Available from: https://etda.libraries.psu.edu/catalog/7904.

Council of Science Editors:

Akdeniz B. IMPROVED NEUTRON KINETICS FOR COUPLED THREE-DIMENSIONAL BOILING WATER REACTOR ANALYSIS. [Doctoral Dissertation]. Penn State University; 2007. Available from: https://etda.libraries.psu.edu/catalog/7904

19. Gosdin, Christopher A. Boiling Water Reactor Simulations, Models, and Benchmarking Using the Thermal Hydraulics Sub-channel Code Ctf.

Degree: MS, Nuclear Engineering, 2015, Penn State University

 CTF, the version of the thermal-hydraulic sub-channel code COBRA-TF being jointly developed and maintained by Pennsylvania State University (PSU) and Oak Ridge National Laboratory (ORNL)… (more)

Subjects/Keywords: CTF; COBRA-TF; BWR; Thermal-Hydraulics

…Figure 38: Varying models of complexity for 2x2 BWR array… …45 Figure 41: Pressure over the axial position for single BWR assembly… …46 Figure 42: Vapor Void Fraction over axial position for single BWR assembly… …48 Figure 43: Pressure over axial position for 2x2 BWR array… …49 Figure 44: Vapor void fraction over axial position for 2x2 BWR array… 

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APA (6th Edition):

Gosdin, C. A. (2015). Boiling Water Reactor Simulations, Models, and Benchmarking Using the Thermal Hydraulics Sub-channel Code Ctf. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/27319

Chicago Manual of Style (16th Edition):

Gosdin, Christopher A. “Boiling Water Reactor Simulations, Models, and Benchmarking Using the Thermal Hydraulics Sub-channel Code Ctf.” 2015. Masters Thesis, Penn State University. Accessed March 20, 2019. https://etda.libraries.psu.edu/catalog/27319.

MLA Handbook (7th Edition):

Gosdin, Christopher A. “Boiling Water Reactor Simulations, Models, and Benchmarking Using the Thermal Hydraulics Sub-channel Code Ctf.” 2015. Web. 20 Mar 2019.

Vancouver:

Gosdin CA. Boiling Water Reactor Simulations, Models, and Benchmarking Using the Thermal Hydraulics Sub-channel Code Ctf. [Internet] [Masters thesis]. Penn State University; 2015. [cited 2019 Mar 20]. Available from: https://etda.libraries.psu.edu/catalog/27319.

Council of Science Editors:

Gosdin CA. Boiling Water Reactor Simulations, Models, and Benchmarking Using the Thermal Hydraulics Sub-channel Code Ctf. [Masters Thesis]. Penn State University; 2015. Available from: https://etda.libraries.psu.edu/catalog/27319


University of Florida

20. Rowe, Mireille. Analysis of Light Water Reactors including 3-D Deterministic Burnup of a Boiling Water Reactor Fuel Assembly.

Degree: MS, Nuclear Engineering Sciences - Nuclear and Radiological Engineering, 2009, University of Florida

 Abstract of Thesis Presented to the Graduate School of the University of Florida in Partial Fulfillment of the Requirements for the Degree of Master of… (more)

Subjects/Keywords: Adjoints; Conceptual lattices; Energy value; Flux density; Fuels; Libraries; Neutrons; Nuclides; Water quality; Water tables; adjoint, burnup, bwr, detector, transport

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APA (6th Edition):

Rowe, M. (2009). Analysis of Light Water Reactors including 3-D Deterministic Burnup of a Boiling Water Reactor Fuel Assembly. (Masters Thesis). University of Florida. Retrieved from http://ufdc.ufl.edu/UFE0024696

Chicago Manual of Style (16th Edition):

Rowe, Mireille. “Analysis of Light Water Reactors including 3-D Deterministic Burnup of a Boiling Water Reactor Fuel Assembly.” 2009. Masters Thesis, University of Florida. Accessed March 20, 2019. http://ufdc.ufl.edu/UFE0024696.

MLA Handbook (7th Edition):

Rowe, Mireille. “Analysis of Light Water Reactors including 3-D Deterministic Burnup of a Boiling Water Reactor Fuel Assembly.” 2009. Web. 20 Mar 2019.

Vancouver:

Rowe M. Analysis of Light Water Reactors including 3-D Deterministic Burnup of a Boiling Water Reactor Fuel Assembly. [Internet] [Masters thesis]. University of Florida; 2009. [cited 2019 Mar 20]. Available from: http://ufdc.ufl.edu/UFE0024696.

Council of Science Editors:

Rowe M. Analysis of Light Water Reactors including 3-D Deterministic Burnup of a Boiling Water Reactor Fuel Assembly. [Masters Thesis]. University of Florida; 2009. Available from: http://ufdc.ufl.edu/UFE0024696

21. Hardgrove, Matthew Thomas. Validation and Application of TRACE/PARCS to Boiling Water Reactor Stability Analysis on the Basis of the OECD/NRC Oskarshamn-2 Benchmark.

Degree: MS, Nuclear Engineering, 2012, Penn State University

 Boiling Water Reactor (BWR) stability is an area of constant research and development to further our understanding. The three main phenomena causing instability in BWRs… (more)

Subjects/Keywords: Oskarshamn-2; BWR Stability; TRACE/PARCS

…88 viii LIST OF ABBREVIATIONS ANM AOOs APRM BiCGSTAB BILU3D BWR CCF CDFs CHAN CMFD CNCC… …Factors BWR Channel Component Coarse Mesh Finite Difference Corrective Nodal Coupling… …attention to this. The most famous incident for BWR stability occurred at LaSalle-2 in Illinois… …oscillations. Coupled neutronic instability is the most important BWR stability phenomenon, because… …core average power. BWR stability is not classified as a safety issue based on the… 

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APA (6th Edition):

Hardgrove, M. T. (2012). Validation and Application of TRACE/PARCS to Boiling Water Reactor Stability Analysis on the Basis of the OECD/NRC Oskarshamn-2 Benchmark. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/13890

Chicago Manual of Style (16th Edition):

Hardgrove, Matthew Thomas. “Validation and Application of TRACE/PARCS to Boiling Water Reactor Stability Analysis on the Basis of the OECD/NRC Oskarshamn-2 Benchmark.” 2012. Masters Thesis, Penn State University. Accessed March 20, 2019. https://etda.libraries.psu.edu/catalog/13890.

MLA Handbook (7th Edition):

Hardgrove, Matthew Thomas. “Validation and Application of TRACE/PARCS to Boiling Water Reactor Stability Analysis on the Basis of the OECD/NRC Oskarshamn-2 Benchmark.” 2012. Web. 20 Mar 2019.

Vancouver:

Hardgrove MT. Validation and Application of TRACE/PARCS to Boiling Water Reactor Stability Analysis on the Basis of the OECD/NRC Oskarshamn-2 Benchmark. [Internet] [Masters thesis]. Penn State University; 2012. [cited 2019 Mar 20]. Available from: https://etda.libraries.psu.edu/catalog/13890.

Council of Science Editors:

Hardgrove MT. Validation and Application of TRACE/PARCS to Boiling Water Reactor Stability Analysis on the Basis of the OECD/NRC Oskarshamn-2 Benchmark. [Masters Thesis]. Penn State University; 2012. Available from: https://etda.libraries.psu.edu/catalog/13890


North Carolina State University

22. Jessee, Matthew Anderson. Cross-Section Adjustment Techniques for BWR Adaptive Simulation.

Degree: PhD, Nuclear Engineering, 2008, North Carolina State University

 Computational capability has been developed to adjust multi-group neutron cross-sections to improve the fidelity of boiling water reactor (BWR) modeling and simulation. The method involves… (more)

Subjects/Keywords: BWR uncertainty analysis; cross-section uncertainty analysis

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APA (6th Edition):

Jessee, M. A. (2008). Cross-Section Adjustment Techniques for BWR Adaptive Simulation. (Doctoral Dissertation). North Carolina State University. Retrieved from http://www.lib.ncsu.edu/resolver/1840.16/4449

Chicago Manual of Style (16th Edition):

Jessee, Matthew Anderson. “Cross-Section Adjustment Techniques for BWR Adaptive Simulation.” 2008. Doctoral Dissertation, North Carolina State University. Accessed March 20, 2019. http://www.lib.ncsu.edu/resolver/1840.16/4449.

MLA Handbook (7th Edition):

Jessee, Matthew Anderson. “Cross-Section Adjustment Techniques for BWR Adaptive Simulation.” 2008. Web. 20 Mar 2019.

Vancouver:

Jessee MA. Cross-Section Adjustment Techniques for BWR Adaptive Simulation. [Internet] [Doctoral dissertation]. North Carolina State University; 2008. [cited 2019 Mar 20]. Available from: http://www.lib.ncsu.edu/resolver/1840.16/4449.

Council of Science Editors:

Jessee MA. Cross-Section Adjustment Techniques for BWR Adaptive Simulation. [Doctoral Dissertation]. North Carolina State University; 2008. Available from: http://www.lib.ncsu.edu/resolver/1840.16/4449


North Carolina State University

23. Kastanya, Doddy Yozef Febrian. Implementation of a Newton-Krylov Iterative Method to Address Strong Non-Linear Feedback Effects in FORMOSA-B BWR Core Simulator.

Degree: PhD, Nuclear Engineering, 2002, North Carolina State University

 A Newton-BICGSTAB solver has been developed to reduce the CPU execution time of the FORMOSA-B boiling water reactor (BWR) core simulator. The new solver treats… (more)

Subjects/Keywords: Neutron diffusion equation; BWR; BICGSTAB; Newton-Krylov

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APA (6th Edition):

Kastanya, D. Y. F. (2002). Implementation of a Newton-Krylov Iterative Method to Address Strong Non-Linear Feedback Effects in FORMOSA-B BWR Core Simulator. (Doctoral Dissertation). North Carolina State University. Retrieved from http://www.lib.ncsu.edu/resolver/1840.16/3915

Chicago Manual of Style (16th Edition):

Kastanya, Doddy Yozef Febrian. “Implementation of a Newton-Krylov Iterative Method to Address Strong Non-Linear Feedback Effects in FORMOSA-B BWR Core Simulator.” 2002. Doctoral Dissertation, North Carolina State University. Accessed March 20, 2019. http://www.lib.ncsu.edu/resolver/1840.16/3915.

MLA Handbook (7th Edition):

Kastanya, Doddy Yozef Febrian. “Implementation of a Newton-Krylov Iterative Method to Address Strong Non-Linear Feedback Effects in FORMOSA-B BWR Core Simulator.” 2002. Web. 20 Mar 2019.

Vancouver:

Kastanya DYF. Implementation of a Newton-Krylov Iterative Method to Address Strong Non-Linear Feedback Effects in FORMOSA-B BWR Core Simulator. [Internet] [Doctoral dissertation]. North Carolina State University; 2002. [cited 2019 Mar 20]. Available from: http://www.lib.ncsu.edu/resolver/1840.16/3915.

Council of Science Editors:

Kastanya DYF. Implementation of a Newton-Krylov Iterative Method to Address Strong Non-Linear Feedback Effects in FORMOSA-B BWR Core Simulator. [Doctoral Dissertation]. North Carolina State University; 2002. Available from: http://www.lib.ncsu.edu/resolver/1840.16/3915


Texas A&M University

24. Solom, Matthew Alan. Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation.

Degree: PhD, Nuclear Engineering, 2016, Texas A&M University

 In current Station Blackout analyses for Generation II Light Water Reactors, battery failure in 4-8 hours is expected to result in the failure of the… (more)

Subjects/Keywords: thermal stratification; chugging; Direct Contact Condensation (DCC); Reactor Core Isolation Cooling (RCIC) System; Boiling Water Reactor (BWR); suppression pool; Station Blackout (SBO)

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APA (6th Edition):

Solom, M. A. (2016). Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/157135

Chicago Manual of Style (16th Edition):

Solom, Matthew Alan. “Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation.” 2016. Doctoral Dissertation, Texas A&M University. Accessed March 20, 2019. http://hdl.handle.net/1969.1/157135.

MLA Handbook (7th Edition):

Solom, Matthew Alan. “Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation.” 2016. Web. 20 Mar 2019.

Vancouver:

Solom MA. Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation. [Internet] [Doctoral dissertation]. Texas A&M University; 2016. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/1969.1/157135.

Council of Science Editors:

Solom MA. Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation. [Doctoral Dissertation]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/157135

25. Skocic, Milan. Etude (photo)-électrochimique en réacteur simulé du phénomène de shadow corrosion des alliages de zirconium : (Photo)-electrochemical study of the shadow corrosion phenomenon of zirconium alloys in simulated reactors.

Degree: Docteur es, Matériaux, mécanique, génie civil, électrochimie, 2016, Grenoble Alpes

Des méthodes électrochimiques classiques, et des caractérisations photoélectrochimiques (PEC), utiliséesex-situ et in-situ, ont permis d’étudier le phénomène de Shadow Corrosion, considéré ici comme une corrosion… (more)

Subjects/Keywords: Photoélectrochimie in-situ; Zircaloy; Alliage de nickel; Conditions REB simulées; Corrosion galvanique; In-situ photoelectrochemistry; Zircaloy; Ni-based alloys; Simulated BWR conditions; Galvanic corrosion; 620

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Skocic, M. (2016). Etude (photo)-électrochimique en réacteur simulé du phénomène de shadow corrosion des alliages de zirconium : (Photo)-electrochemical study of the shadow corrosion phenomenon of zirconium alloys in simulated reactors. (Doctoral Dissertation). Grenoble Alpes. Retrieved from http://www.theses.fr/2016GREAI015

Chicago Manual of Style (16th Edition):

Skocic, Milan. “Etude (photo)-électrochimique en réacteur simulé du phénomène de shadow corrosion des alliages de zirconium : (Photo)-electrochemical study of the shadow corrosion phenomenon of zirconium alloys in simulated reactors.” 2016. Doctoral Dissertation, Grenoble Alpes. Accessed March 20, 2019. http://www.theses.fr/2016GREAI015.

MLA Handbook (7th Edition):

Skocic, Milan. “Etude (photo)-électrochimique en réacteur simulé du phénomène de shadow corrosion des alliages de zirconium : (Photo)-electrochemical study of the shadow corrosion phenomenon of zirconium alloys in simulated reactors.” 2016. Web. 20 Mar 2019.

Vancouver:

Skocic M. Etude (photo)-électrochimique en réacteur simulé du phénomène de shadow corrosion des alliages de zirconium : (Photo)-electrochemical study of the shadow corrosion phenomenon of zirconium alloys in simulated reactors. [Internet] [Doctoral dissertation]. Grenoble Alpes; 2016. [cited 2019 Mar 20]. Available from: http://www.theses.fr/2016GREAI015.

Council of Science Editors:

Skocic M. Etude (photo)-électrochimique en réacteur simulé du phénomène de shadow corrosion des alliages de zirconium : (Photo)-electrochemical study of the shadow corrosion phenomenon of zirconium alloys in simulated reactors. [Doctoral Dissertation]. Grenoble Alpes; 2016. Available from: http://www.theses.fr/2016GREAI015

26. Gupta, Atul. Development of Boiling Water Reactor Nuclear Power Plant Simulator for Human Reliability Analysis Education and Research.

Degree: MS, Mechanical Engineering, 2013, The Ohio State University

 This thesis discusses the development of Full scope BWR Simulator developed for human reliability course initiated at The Ohio State University. Human System Interface (HSI)… (more)

Subjects/Keywords: Mechanical Engineering; Human reliability analysis; human factors; BWR simulator

…3.4.2 BWR Reactor Assembly… …115 Figure 33: The ECCS systems in a BWR. HPCI is pink, ADS is yellow, LPCS is green and… …were followed to create a “Basic Principles Simulator” from the “Full Scope BWR Simulator… …Boiling Water Reactor NPP Simulator OSU NuSim is based on a BWR (Boiling Water Reactor… …BWR Simulator. Users There are three user accounts for normal operation of the Simulator… 

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Gupta, A. (2013). Development of Boiling Water Reactor Nuclear Power Plant Simulator for Human Reliability Analysis Education and Research. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1355347881

Chicago Manual of Style (16th Edition):

Gupta, Atul. “Development of Boiling Water Reactor Nuclear Power Plant Simulator for Human Reliability Analysis Education and Research.” 2013. Masters Thesis, The Ohio State University. Accessed March 20, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1355347881.

MLA Handbook (7th Edition):

Gupta, Atul. “Development of Boiling Water Reactor Nuclear Power Plant Simulator for Human Reliability Analysis Education and Research.” 2013. Web. 20 Mar 2019.

Vancouver:

Gupta A. Development of Boiling Water Reactor Nuclear Power Plant Simulator for Human Reliability Analysis Education and Research. [Internet] [Masters thesis]. The Ohio State University; 2013. [cited 2019 Mar 20]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1355347881.

Council of Science Editors:

Gupta A. Development of Boiling Water Reactor Nuclear Power Plant Simulator for Human Reliability Analysis Education and Research. [Masters Thesis]. The Ohio State University; 2013. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1355347881


KTH

27. Fager, Fredrick. Nuclear Waste Canister : Evaluating the mechanical properties of cassette steel after casting.

Degree: Materials Science and Engineering, 2017, KTH

Företaget Svensk Kärnbränslehantering AB (SKB) håller på att utveckla en slutförvaringskapsel som kommer innehålla avfall från den svenska kärnkraften. Det är dock fortfarande en… (more)

Subjects/Keywords: Nuclear waste canister; Steel; nodular cast iron; carbon diffusion; microstructure; chemical composition; mechanical properties; pearlite; ferrite; BWR; radioactive; Metallurgy and Metallic Materials; Metallurgi och metalliska material

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Fager, F. (2017). Nuclear Waste Canister : Evaluating the mechanical properties of cassette steel after casting. (Thesis). KTH. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-209803

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):

Fager, Fredrick. “Nuclear Waste Canister : Evaluating the mechanical properties of cassette steel after casting.” 2017. Thesis, KTH. Accessed March 20, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-209803.

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

MLA Handbook (7th Edition):

Fager, Fredrick. “Nuclear Waste Canister : Evaluating the mechanical properties of cassette steel after casting.” 2017. Web. 20 Mar 2019.

Vancouver:

Fager F. Nuclear Waste Canister : Evaluating the mechanical properties of cassette steel after casting. [Internet] [Thesis]. KTH; 2017. [cited 2019 Mar 20]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-209803.

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

Council of Science Editors:

Fager F. Nuclear Waste Canister : Evaluating the mechanical properties of cassette steel after casting. [Thesis]. KTH; 2017. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-209803

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

28. Aydogan, Fatih. DEVELOPMENT OF UNCERTAINTY METHODOLOGY FOR COBRA-TF VOID DISTRIBUTION AND CRITICAL POWER PREDICTIONS.

Degree: PhD, Nuclear Engineering, 2008, Penn State University

 Thermal hydraulic codes are commonly used tools in licensing processes for the evaluation of various thermal hydraulic scenarios. The uncertainty of a thermal hydraulic code… (more)

Subjects/Keywords: dry-out elevation; uncertainty analysis; bwr; cobra-tf; fatih aydogan; pennstate uncertainty methodology; void distribution; critical power; bwr bundle

…Interfacial Heat Transfer Area Per Unit Volume .21 Table 4.1. Dimensions of BWR Test… …Evaluation of the Uncertainty …90 Table 6.1. PIRT for Steady State Void Distribution in BWR Bundle… …either Pressurized Water Reactor (PWR) or Boiling Water Reactor (BWR) type… …phase flow. Because of two phase flow, a BWR has more flow regimes in its reactor than a PWR… …other words, uncertainty analyses of the BWR steady state nominal and transient condition… 

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Aydogan, F. (2008). DEVELOPMENT OF UNCERTAINTY METHODOLOGY FOR COBRA-TF VOID DISTRIBUTION AND CRITICAL POWER PREDICTIONS. (Doctoral Dissertation). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/8179

Chicago Manual of Style (16th Edition):

Aydogan, Fatih. “DEVELOPMENT OF UNCERTAINTY METHODOLOGY FOR COBRA-TF VOID DISTRIBUTION AND CRITICAL POWER PREDICTIONS.” 2008. Doctoral Dissertation, Penn State University. Accessed March 20, 2019. https://etda.libraries.psu.edu/catalog/8179.

MLA Handbook (7th Edition):

Aydogan, Fatih. “DEVELOPMENT OF UNCERTAINTY METHODOLOGY FOR COBRA-TF VOID DISTRIBUTION AND CRITICAL POWER PREDICTIONS.” 2008. Web. 20 Mar 2019.

Vancouver:

Aydogan F. DEVELOPMENT OF UNCERTAINTY METHODOLOGY FOR COBRA-TF VOID DISTRIBUTION AND CRITICAL POWER PREDICTIONS. [Internet] [Doctoral dissertation]. Penn State University; 2008. [cited 2019 Mar 20]. Available from: https://etda.libraries.psu.edu/catalog/8179.

Council of Science Editors:

Aydogan F. DEVELOPMENT OF UNCERTAINTY METHODOLOGY FOR COBRA-TF VOID DISTRIBUTION AND CRITICAL POWER PREDICTIONS. [Doctoral Dissertation]. Penn State University; 2008. Available from: https://etda.libraries.psu.edu/catalog/8179

29. Constanda, Daniel. Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate.

Degree: Applied Nuclear Physics, 2015, Uppsala University

  This study aims to improve the modeling of partial SCRAM in the BISON plant model for the Forsmark 2 nuclear reactor after power uprate.… (more)

Subjects/Keywords: nuclear power; bwr; boiling water reactor; BISON; POLCA; partial SCRAM modeling; control rod effect; transients

…Water Reactor A Boiling Water Reactor (BWR) is one of the two most common light… …difference is what gives them their names, the water inside the reactor of a BWR is boiling but in… …a PWR it is not due to the higher pressure in the reactor. Another difference is that BWR… …the PWR needs a steam generator in order to get steam to drive the turbine. The BWR already… …hereby simply referred to as Forsmark) are of BWR type. Thus this report will only focus… 

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Constanda, D. (2015). Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-269360

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):

Constanda, Daniel. “Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate.” 2015. Thesis, Uppsala University. Accessed March 20, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-269360.

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

MLA Handbook (7th Edition):

Constanda, Daniel. “Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate.” 2015. Web. 20 Mar 2019.

Vancouver:

Constanda D. Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate. [Internet] [Thesis]. Uppsala University; 2015. [cited 2019 Mar 20]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-269360.

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

Council of Science Editors:

Constanda D. Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate. [Thesis]. Uppsala University; 2015. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-269360

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

30. Zhao, Shi. 3D real-time stockpile mapping and modelling with accurate quality calculation using voxels.

Degree: 2016, University of Adelaide

 Stockpile blending is widely accepted as an effective method to reduce the short-term quality variations and optimise the homogeneity of bulk materials, such as iron… (more)

Subjects/Keywords: stockpile management; 3D modelling; iron ore quality control; BWR; localization; UKF

…volume is better than 0.2%. Therefore, the combination of stock- xii pile and BWR (… …automatically in real-time and the integration of the stockpile and BWR model generates a novel… …Innovations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 BWR Localization for… …30 3.1.3 UKF Sensor Data Fusion for BWR Localization . . . . . . . . . . 32 Simulation… …4.6 5 Quality Estimation and BWR Automation 5.1 5.2 5.3 101 3D Stockpile Management… 

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Zhao, S. (2016). 3D real-time stockpile mapping and modelling with accurate quality calculation using voxels. (Thesis). University of Adelaide. Retrieved from http://hdl.handle.net/2440/103494

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):

Zhao, Shi. “3D real-time stockpile mapping and modelling with accurate quality calculation using voxels.” 2016. Thesis, University of Adelaide. Accessed March 20, 2019. http://hdl.handle.net/2440/103494.

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

MLA Handbook (7th Edition):

Zhao, Shi. “3D real-time stockpile mapping and modelling with accurate quality calculation using voxels.” 2016. Web. 20 Mar 2019.

Vancouver:

Zhao S. 3D real-time stockpile mapping and modelling with accurate quality calculation using voxels. [Internet] [Thesis]. University of Adelaide; 2016. [cited 2019 Mar 20]. Available from: http://hdl.handle.net/2440/103494.

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

Council of Science Editors:

Zhao S. 3D real-time stockpile mapping and modelling with accurate quality calculation using voxels. [Thesis]. University of Adelaide; 2016. Available from: http://hdl.handle.net/2440/103494

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

[1] [2]

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