| Tài liệu tham khảo |
Loại |
Chi tiết |
| 1. A. Shestopalov, K Lioutov, L. Yegorova (2003), “Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR Transient Codes and Updating of MATPRO Package for Modeling of LOCA and RIA Validation Cases with Zr-1%Nb (VVER type) Cladding”, Nuclear Safety Institute of the Russian Research Centre, Kurchatov Institute |
Sách, tạp chí |
| Tiêu đề: |
Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR Transient Codes and Updating of MATPRO Package for Modeling of LOCA and RIA Validation Cases with Zr-1%Nb (VVER type) Cladding |
| Tác giả: |
A. Shestopalov, K Lioutov, L. Yegorova |
| Năm: |
2003 |
|
| 2. A. Shestopalov, K. Lioutov, L. Yegorova, G. Abyshov, K. Mikitiouk (1999), “Modification of USNRC's FRAP-T6 Fuel Rod Transient Code for High Burnup VVER Fuel”, Moscow, Russia |
Sách, tạp chí |
| Tiêu đề: |
Modification of USNRC's FRAP-T6 Fuel Rod Transient Code for High Burnup VVER Fuel |
| Tác giả: |
A. Shestopalov, K. Lioutov, L. Yegorova, G. Abyshov, K. Mikitiouk |
| Năm: |
1999 |
|
| 3. Antti Daavittila, Anitta Hamalaimen, Hanna Raty (2005), “Transient and Fuel performance analysis with VTT’s coupled code system”, American Nuclear Society, LaGrange Park, IL |
Sách, tạp chí |
| Tiêu đề: |
Transient and Fuel performance analysis with VTT’s coupled code system |
| Tác giả: |
Antti Daavittila, Anitta Hamalaimen, Hanna Raty |
| Năm: |
2005 |
|
| 4. Baker, L. Just, L.C. (05/1962), “Studies of metal-water reactions at high temperatures. III. Experimental and theoretical studies of the zirconium-water reaction”, Argonne National Laboratory, ANL 6548 |
Sách, tạp chí |
| Tiêu đề: |
Studies of metal-water reactions at high temperatures. III. Experimental and theoretical studies of the zirconium-water reaction |
|
| 6. Federal Atomic Energy Agency (2011), “Novovoronezh NPP-2 Power unit No.1: Preliminary Safety Analysis Report” |
Sách, tạp chí |
| Tiêu đề: |
Novovoronezh NPP-2 Power unit No.1: Preliminary Safety Analysis Report |
| Tác giả: |
Federal Atomic Energy Agency |
| Năm: |
2011 |
|
| 7. Jinzhao ZHANG, Zeynab UMIDOVA, Adrieu DETHIOUX (2-5/9/2012), “Qualification of FRAPCON/FRAPTRAN codes for fuel rod design verification and fuel safety evaluation”, Transactions of the 2012 International Meeting on LWR Fuel Performance (TopFuel 2012), Manchester, UK |
Sách, tạp chí |
| Tiêu đề: |
Qualification of FRAPCON/FRAPTRAN codes for fuel rod design verification and fuel safety evaluation |
|
| 8. Jinzhao Zhang (11/2013), “Simulation of fuel behaviors under LOCA and RIA using FRAPTRAN code and uncertainty analysis with DAKOTA” IAEA Technical Meeting on Modeling of Water-Cooled Fuel Including Design Basis and Severe Accidents, China |
Sách, tạp chí |
| Tiêu đề: |
Simulation of fuel behaviors under LOCA and RIA using FRAPTRAN code and uncertainty analysis with DAKOTA |
|
| 9. J. R. Wang, W. Y. Li, H. T. Lin, J. H. Yang, C. Shih, S. W. Chen (2014), “The analysis of TRACE/FRAPTRAN in the fuel rods of Maanshan PWR for LBLOCA”, International Journal of Physical and Mathematical Sciences, Vol.8, No.1 |
Sách, tạp chí |
| Tiêu đề: |
The analysis of TRACE/FRAPTRAN in the fuel rods of Maanshan PWR for LBLOCA |
| Tác giả: |
J. R. Wang, W. Y. Li, H. T. Lin, J. H. Yang, C. Shih, S. W. Chen |
| Năm: |
2014 |
|
| 11. K.J. Geelhood, W.G. Luscher and C.E. Beyer (2014), “FRAPTRAN 1.5: Integral Assessment”, NUREG/CR-7022, Vol.2, US NRC |
Sách, tạp chí |
| Tiêu đề: |
FRAPTRAN 1.5: Integral Assessment |
| Tác giả: |
K.J. Geelhood, W.G. Luscher and C.E. Beyer |
| Năm: |
2014 |
|
| 14. Pettersson, K. and Haag, Y. (03/1980), “Deformation and failure of Zircaloy cladding in a LOCA. Effects of preoxidation and fission products on deformation and fracture behaviour. SKI project B23/78”, Studsvik Energiteknik AB, STUDSVIK/K4-80/13 |
Sách, tạp chí |
| Tiêu đề: |
Deformation and failure of Zircaloy cladding in a LOCA. Effects of preoxidation and fission products on deformation and fracture behaviour. SKI project B23/78 |
|
| 15. R. Hosmer Norris, Florence F.Buckland, Nancy D.Fitzroy, Roy H.Roecker (1983), “Data book – Heat Transfer and Fluid Flow”, General Electric Company, Schenectady N.Y |
Sách, tạp chí |
| Tiêu đề: |
Data book – Heat Transfer and Fluid Flow |
| Tác giả: |
R. Hosmer Norris, Florence F.Buckland, Nancy D.Fitzroy, Roy H.Roecker |
| Năm: |
1983 |
|
| 5. Đỗ Ngọc Điệp, Phùng Khắc Toàn, “Using FRAPTRAN 1.5 code for safety evaluation of TVS-2006 fuel rod under transient conditions of VVER-1200 (AES- 2006) reactor, Tập 3, Tạp chí Nuclear Science and Technology (ISSN 1810-5408, Việt Nam), năm 2015 |
Khác |
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| 12. Neil E. Todreas, Mujid S. Kazimi, Massachusetts Institute of Technology, Nuclear systems I - Thermal Hydraulic Fundamentals |
Khác |
|
| 16. U.S.Nuclear Regulatory Commission, NUREG-0800 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, USA, 03/2007 |
Khác |
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