| Tài liệu tham khảo |
Loại |
Chi tiết |
| 1. A. Shestopalov, K Lioutov, L. Yegorova, “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", 2003 |
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”, Nuclear Safety Institute of the Russian Research Centre "Kurchatov Institute |
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| 4. Federal Atomic Energy Agency, “Novovoronezh NPP-2 Power unit No.1: Preliminary Safety Analysis Report”, 2011 |
Sách, tạp chí |
| Tiêu đề: |
Novovoronezh NPP-2 Power unit No.1: Preliminary Safety Analysis Report |
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| 6. Jimmy Sudjana, Zeynab Umidova, Jinzhao Zhang, Maxime Haedens and Christophe Schneidesch, "Evaluation of PWR Rod Ejection Accident Margins Using PANTHER/COBRA and FRAPTRAN," Proceedings of LWR Fuel Performance Meeting TopFuel 2013, Charlotte, NC, USA, September 15 - 19, 2013 |
Sách, tạp chí |
| Tiêu đề: |
Evaluation of PWR Rod Ejection Accident Margins Using PANTHER/COBRA and FRAPTRAN |
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| 7. Jinzhao Zhang, “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, November, 2013 |
Sách, tạp chí |
| Tiêu đề: |
Simulation of fuel behaviors under LOCA and RIA using FRAPTRAN code and uncertainty analysis with DAKOTA |
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| 8. K.J. Geelhood, W.G. Luscher, C.E. Beyer, J.M. Cuta, “FRAPTRAN 1.5: A Computer Code for the Transient Analysis of Oxide Fuel Rods”, NUREG/CR-7023 |
Sách, tạp chí |
| Tiêu đề: |
FRAPTRAN 1.5: A Computer Code for the Transient Analysis of Oxide Fuel Rods |
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| 9. K.J. Geelhood, W.G. Luscher and C.E. Beyer, “FRAPTRAN 1.5: Integral Assessment”, NUREG/CR-7022, Vol.2, US NRC, 2014 |
Sách, tạp chí |
| Tiêu đề: |
FRAPTRAN 1.5: Integral Assessment |
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| 10. K.J. Geelhood, W.G. Luscher and C.E. Beyer, “FRAPCON-3.4: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup”, NUREG/CR-7022, Vol.1, US NRC, 2014 |
Sách, tạp chí |
| Tiêu đề: |
FRAPCON-3.4: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup |
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| 2. Alfred Strasser, Aquarius Services, Sleepy Hollow, NY, USA. Friedrich Garzarolli Fürth, Germany. Peter Rudling ANT International, Skultuna, Sweden:Processes going on in Nonfailed Rod during Accident Conditions (LOCA and RIA), Volume II |
Khác |
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| 3. A.R.Massih, L.O.Jernkvist, J.E.Lindback, G.Zhou: Analysis of PCI of LWR Fuel rods during power ramps, Beijing, China, 7-12/08/2005 |
Khác |
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| 5. P.J.Pankaskie: The Impact of Pellet-Cladding Interaction on Fuel Integrity – A Status Report, USNRC, 02/1978 |
Khác |
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| 11. Martin A.Zimmermann: Nuclear fuel - Fuel behavior under RIA and LOCA, 20/12/2007 |
Khác |
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| 12. Zir-11 special topic report: Pellet-cladding interaction (PCI and PCMI), ANT international, Sweden, 10/2006 |
Khác |
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