Modeling Fragmentation and Spallation of Oxide Reactor Fuel During Transient Heating Including the Effects of Burnup and Fission Product Distribution
Author:
Affiliation:
1. Argonne National Laboratory, Reactor Analysis and Safety Division 9700 South Cass Avenue, Argonne, Illinois 60439
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/NT83-A33231
Reference7 articles.
1. L. W. DEITRICH and J. F. JACKSON, “Summary Report on the Specialists’ Meeting on the Role of Fission Products in Whole Core Accidents,” IWGFR/19, Atomic Energy Research Establishment Harwell (1977).
2. O. D. SLAGLE, C. A. HINMAN, and E. T. WEBER, “Experiments on Melting and Gas Release Behavior of Irradiated Fuel,” HEDL-TME 74-17, Hanford Engineering Development Laboratory (Sep. 1974).
3. Effect of Burnup on the Response of Stainless Steel-Qad Mixed-Oxide Fuels to Simulated Thermal Transients
4. C. A. HINMAN and S. K. FUKUDA, Hanford Engineering Development Laboratory, Private Communication (1981).
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