LARC-1: a Los Alamos release calculation program for fission product transport in HTGRs during the LOFC accident
The theoretical and numerical data base development of the LARC-1 code is described. Four analytical models of fission product release from an HTGR core during the loss of forced circulation accident are developed. Effects of diffusion, adsorption and evaporation of the metallics and precursors are neglected in this first LARC model. Comparison of the analytic models indicates that the constant release-renormalized model is adequate to describe the processes involved. The numerical data base for release constants, temperature modeling, fission product release rates, coated fuel particle failure fraction and aged coated fuel particle failure fractions is discussed. Analytic fits and graphic displays for these data are given for the Ft. St. Vrain and GASSAR models.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36; DON-ARPA-N00014-75C-0661
- OSTI ID:
- 7334838
- Report Number(s):
- LA-NUREG-6563-MS; TRN: 77-005698
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
L CODES
FISSION PRODUCT RELEASE
HTGR TYPE REACTORS
LOSS OF FLOW
RADIOACTIVITY TRANSPORT
COATED FUEL PARTICLES
CONTAINMENT
REACTOR ACCIDENTS
ACCIDENTS
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GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
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Graphite Moderated