Water reactor fuel performance codeprofess and its application for predicting the behaviour of the fuel elements of D-Com blind problem
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OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics
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References (12)
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1. Hilbert R F, Storhok V W, Chubb W and Keller D C 1971J. Nucl. Mater. 38 2610.1016/0022-3115(71)90004-3 ↗
2. Hoppe N, Billaus M and Vliet J U 1982 Belgonuclair Report COMETHE III-L, Report No. BN 8201/-04
3. Misfeldt I 1982 Data for The D-Com blind problem on fission gas release, Report B-528, Metallurgy Dept., RISØ National Laboratory, Denmark
4. Misfeldt I 1983OECD-NEA-CSNI/IAEA Specialists meeting on Water Reactor Fuel Safety and Fission Gas release in off normal and Accident Condition, RISØ National Laboratory, Denmark
5. Pati S R and Ritterbusch S E 1980Fission gas release during anticipated transient; IAEA Specialists Meeting on Water Reactor Fuel Element Performances Modelling, Blackpool, UK
6. Pedersen N K 1978Proc. IAEA Specialists Meeting on Water Reactor Fuel Performance Computer Modelling, Blackpool, U K
7. Ross A M and Stout R L 1962 Heat Transfer Coefficient between UO2 and Zircaloy-2, Report AECL 1552.
8. Roy P R and Sah D N 1985Pramana (J. Phys.) 24 39710.1007/BF02894841 ↗
9. Sah D N, Venkatesh D and Sivaramakrishnan K S 1983Proc. Symp. on Irradiation Effects in Solids (Bombay: BARC) p. 203
10. Sah D N, Venkatesh D and Ramadasan E 1984IAEA Specialists Meeting on Water Reactor Fuel Element Performance Modelling, Bowness on Windermere UK (to be published).
11. Wood D S and Watkins B 1971J. Nucl. Mater. 41 32710.1016/0022-3115(71)90170-X ↗
12. Zimmermann H 1979IAEA Specialists Meeting on Behaviour of defected zirconium alloy clad ceramic fuel in water cooled reactors, Chalk River, Canada p. 147