| Tài liệu tham khảo |
Loại |
Chi tiết |
| [1] A. Rubin et al. (2010) OECD/NRC Benchmark Based on NUPEC PWR Sub channel and Bundle Tests (PSBT), Volume I: Experimental Database and Final Problem Specifications.US NRC/ OECD Nuclear Energy Agency, November 2010, pp. 12-22 |
Sách, tạp chí |
| Tiêu đề: |
OECD/NRC Benchmark Based on NUPEC PWR Sub channel and Bundle Tests (PSBT), Volume I: Experimental Database and Final Problem Specifications |
|
| [2] André Bakker (2006) Lecture 11 – Boundary Layers and Separation, Applied Computational Fluid Dynamics. Lecture in Dartmouth College from 2002-2006.http://www.bakker.org/dartmouth06/engs150/ |
Sách, tạp chí |
| Tiêu đề: |
Lecture 11 – Boundary Layers and Separation, Applied Computational Fluid Dynamics |
|
| [4] Boštjan Koncar, Borut Mavko (2002) Modeling of low-pressure sub cooled flow boiling using the RELAP5 code. Nuclear Engineering and Design 220 (2003) 255–273 |
Sách, tạp chí |
| Tiêu đề: |
Modeling of low-pressure sub cooled flow boiling using the RELAP5 code |
|
| [5] Boyan Ivanov, Kostadin Ivanov, Pavlin Groudev, Malinka Pavlova, Vasil Hadjiev, NEA/NSC/DOC (2002) VVER-1000 Coolant Transient Benchmark. PHASE 1 (V1000CT-1) Vol. I: Main Coolant Pump (MCP) switching On - Final Specifications. NUCLEAR ENERGY AGENCYORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT, 2002, pp. 87-88 |
Sách, tạp chí |
| Tiêu đề: |
VVER-1000 Coolant Transient Benchmark. PHASE 1 (V1000CT-1) Vol. I: Main Coolant Pump (MCP) switching On - Final Specifications |
|
| [6] Brian L. Smith (2010) Assessment of CFD codes used in nuclear reactor safety simulations. Nuclear Engineering and Technology, Vol.42 No.4, pp.339 - 364, August 2010 |
Sách, tạp chí |
| Tiêu đề: |
Assessment of CFD codes used in nuclear reactor safety simulations |
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| [7] Bub Dong Chung, Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute (2009) Introduction of System T/H Safety Analysis Code. VAEI Training Course on Fundamental Safety Analysis and Computer Code with Basic T/H Knowledge Requirements, October 12-16, 2009, Hanoi, Vietnam |
Sách, tạp chí |
| Tiêu đề: |
Introduction of System T/H Safety Analysis Code |
|
| [8] C.Baudry, M.Guingo, A.Douce, J.Lavi´eville, S. Mimouni, and M. Boucker (2012) Numerical Study of the Steady-State Sub channel Test-Case with NEPTUNE CFD for the OECD/NRC NUPEC PSBT Benchmark. Science and Technology of Nuclear Installations, Volume 2012, Article ID 524598. Accepted 27 July 2012 |
Sách, tạp chí |
| Tiêu đề: |
Numerical Study of the Steady-State Sub channel Test-Case with NEPTUNE CFD for the OECD/NRC NUPEC PSBT Benchmark |
|
| [9] Dominique Bestion (2008) System Code Models and Capabilities. THICKET 2008 – Session III – Paper 06 |
Sách, tạp chí |
| Tiêu đề: |
System Code Models and Capabilities |
|
| [10] Dominique Bestion (2010) Extension of CFD codes application to two-phase flow safety problems. Nuclear Engineering and Technology, Vol.42 No.4, pp. 365-376, August 2010 |
Sách, tạp chí |
| Tiêu đề: |
Extension of CFD codes application to two-phase flow safety problems |
|
| [11] Dominique Bestion (2011) Status and Perspective for a multi scale approach to Light Water Reactor thermal hydraulic simulation. The 14th International Topical Meeting on Nuclear Reactor Thermal hydraulics, NURETH-14 Toronto, Ontario, Canada, September 25- 30, 2011 |
Sách, tạp chí |
| Tiêu đề: |
Status and Perspective for a multi scale approach to Light Water Reactor thermal hydraulic simulation |
|
| [12] E. Krepper, R. Rzehak (2011) CFD ANALYSIS OF A VOID DISTRIBUTION BENCHMARK OF THE NUPEC PSBT TESTS. Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH ’14) , Hilton Toronto Hotel, Toronto, Ontario, Canada, September 25-29, 2011 |
Sách, tạp chí |
| Tiêu đề: |
CFD ANALYSIS OF A VOID DISTRIBUTION BENCHMARK OF THE NUPEC PSBT TESTS |
|
| [14] Eckhard Krepper, Bostjan Koncar, Yury Egorov (2006) CFD modeling of sub cooled boiling—Concept, validation and application to fuel assembly design. Nuclear Engineering and Design 237 (2007) 716–731 |
Sách, tạp chí |
| Tiêu đề: |
CFD modeling of sub cooled boiling—Concept, validation and application to fuel assembly design |
|
| [15] Expert Group on Reactor - based Plutonium Disposition, Eugeny Gomin, Mikhail Kalugin, Dmitry Oleynik Russian Research Centre, Kurchatov Institute (2006) VVER-1000 MOX core Computational Benchmark, Specification and Results. OECD 2006, NEA No 6088 |
Sách, tạp chí |
| Tiêu đề: |
VVER-1000 MOX core Computational Benchmark, Specification and Results |
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| [16] G. Rabello dos Anjos, Jacopo Buongiorno (2013) Bubble Condensation Heat Transfer in Subcooled Flow Boiling at PWR Conditions: a Critical Evaluation of Current Correlations.Massachusetts Institute of Technology Cambridge, MA, USA September 2013, pp. 8-11 |
Sách, tạp chí |
| Tiêu đề: |
Bubble Condensation Heat Transfer in Subcooled Flow Boiling at PWR Conditions: a Critical Evaluation of Current Correlations |
|
| [17] H. Anglart, O. Nylund, N. Kurul, and M. Z. Podowski (1997) CFD prediction of flow and phase distribution in fuel assemblies with spacers. Proceedings of the NURETH-7, Saratoga Springs, New York, 1995, published in: Nuclear Eng. & Design (NED), Vol. 177, pp. 215-228, 1997 |
Sách, tạp chí |
| Tiêu đề: |
CFD prediction of flow and phase distribution in fuel assemblies with spacers |
|
| [18] Information Systems Laboratories, Inc., Rockville, Maryland, Idaho Falls, Idaho (2001) RELAP5/MOD3.3 Code Manual, Vol. II, Appendix A Input Requirements. December 2001, pp. 12, 234 |
Sách, tạp chí |
| Tiêu đề: |
RELAP5/MOD3.3 Code Manual, Vol. II, Appendix A Input Requirements |
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| [19] Information Systems Laboratories, Inc., Rockville, Maryland, Idaho Falls, Idaho (2001) RELAP5/MOD3.3 Code Manual, Vol. I Code structure, System models, and Solution methods.December 2001, pp. 16-20, 20-24, 95 |
Sách, tạp chí |
| Tiêu đề: |
RELAP5/MOD3.3 Code Manual, Vol. I Code structure, System models, and Solution methods |
|
| [20] Information Systems Laboratories, Inc., Rockville, Maryland, Idaho Falls, Idaho (2001) RELAP5/MOD3.3 Code Manual, Vol. IV Models and Correlations. December 2001, pp. 39- 105, 211-213 |
Sách, tạp chí |
| Tiêu đề: |
RELAP5/MOD3.3 Code Manual, Vol. IV Models and Correlations |
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| [21] International Atomic Energy Agency (2003) Accident analysis for Nuclear Power Plants with Pressurized Water Reactors. Safety Reports Series No. 30, Vienna 2003, pp. 8-11 |
Sách, tạp chí |
| Tiêu đề: |
Accident analysis for Nuclear Power Plants with Pressurized Water Reactors |
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| [22] International Atomic Energy Agency (2008) Best estimate safety analysis for nuclear power plants: uncertainty evaluation. Safety Reports Series No. 52, Vienna 2008, pp. 1-2 |
Sách, tạp chí |
| Tiêu đề: |
Best estimate safety analysis for nuclear power plants: uncertainty evaluation |
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