Preliminary topical report on comparison reactor disassembly calculations
Preliminary results of comparison disassembly calculations for a representative LMFBR model (2100-l voided core) and arbitrary accident conditions are described. The analytical methods employed were the computer programs: FX2- POOL, PAD, and VENUS-II. The calculated fission energy depositions are in good agreement, as are measures of the destructive potential of the excursions, kinetic energy, and work. However, in some cases the resulting fuel temperatures are substantially divergent. Differences in the fission energy deposition appear to be attributable to residual inconsistencies in specifying the comparison cases. In contrast, temperature discrepancies probably stem from basic differences in the energy partition models inherent in the codes. Although explanations of the discrepancies are being pursued, the preliminary results indicate that all three computational methods provide a consistent, global characterization of the contrived disassembly accident. (auth)
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- NSA Number:
- NSA-33-014120
- OSTI ID:
- 4112909
- Report Number(s):
- LA-6106-MS
- Resource Relation:
- Other Information: Orig. Receipt Date: 30-JUN-76
- Country of Publication:
- United States
- Language:
- English
Similar Records
Improved and verification of fast reactor safety analysis techniques. Annual summary, March 1, 1975--February 29, 1976
Improvement and verification of fast reactor safety analysis techniques
Related Subjects
N77500 -Reactors-Power Reactors
Breeding
220900* -Nuclear Reactor Technology-Reactor Safety
*LMFBR TYPE REACTORS- REACTOR CORE DISRUPTION
*REACTOR CORE DISRUPTION- ENERGY YIELD
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
EXCURSIONS
F CODES
P CODES
V CODES