Fission Gas Behavior in Fast Reactor Fuel under Transient Power Conditions
Author:
Affiliation:
1. University of California, School of Engineering and Applied Science, Energy and Kinetics Department, Los Angeles, California 90024
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT74-A31458
Reference29 articles.
1. D. D. FREEMAN, E. G. LEFF, D. J. BENDER, and W. G. MEINHARDT, “The FREADM-1 Code, A Fast Reactor Excursion and Accident Dynamics Model,” GEAP-13608, Breeder Reactor Development Operation, General Electric Company, Sunnyvale, Califomia (1970).
2. A. E. WALTER, A. PADILLA, Jr., and R. J. SHIELDS, “MELT-II, A Two-Dimensional Neutronics-Heat Transfer Program for Fast Reactor Safety Analysis,” HEDL-TME 72-43, Hanford Engineering Development Laboratory, Richland, Washington (Apr. 1972).
3. N. HIRAKAWA, “MARS, A Two-Dimensional Excursion Code,” APDA-198, Atomic Power Development Associates, Detroit, Michigan (June 1967).
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