Core burnup calculation and accidents analyses of a pressurized water reactor partially loaded with rock-like oxide fuel

Journal of Nuclear Materials

Volumn 319, Issue , 2003, Pages 166-172

  Akie, H ^a   Sugo, Y ^b   Okawa, R ^c  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b Information Technologies Japan Inc   (Japan)

^c Scientific Research Institute Ltd   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

LOSS OF COOLANT ACCIDENTS; NUCLEAR FUELS; REACTIVITY (NUCLEAR); REACTOR CORES;

POWER PEAKING;

PRESSURIZED WATER REACTORS;

EID: 0038696345     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(03)00147-8     Document Type: Conference Paper

References (5)

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3. N. Ohnishi, T. Harami, H. Hirose, M. Uemura, EUREKA-2: A Computer Code for the Reactivity Accident Analysis in a Water Cooled Reactor, Japan Atomic Energy Research Institute Report JAERI-M 84-074, 1984 (in Japanese).
4. C.E. Peterson, J.H. McFadden, M.P. Paulsen, G.C. Gose, RETRAN-02 - A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems, Electric Power Research Institute Report EPRI NP-1850 CCM, 1, 1981.
5. Nakamura T., Kusagaya K., Yoshinaga M., Uetsuka H., Yamashita T. Prog. Nucl. Energy. 38:2001;379.