Some Recriticality Studies with SIMMER-II. [LMFBR]

Conference · Sun Aug 19 04:00:00 EDT 1979

OSTI ID:5981618

Bohl, W. R. ^[1]

---

1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

The SIMMER-II code was applied to the problem of evaluating the potential for recriticality in an LMFBR HCDA. The phenomenology examined was based on the post SAS3D behavior in a CRBR LOF accident. The SIMMER-II results were found to be sensitive to the development of fuel blockages. If blockages were formed close to the core, the core-disruption phase of the behavior resulted from the significant energy required following SAS3D termination to raise the average steel temperature to saturation conditions; also, material deposition near heat sinks eliminated condensation surfaces and induced core pressurization and fuel collapse. Excessive ramp rates (greater than $100/s) were judged to be unlikely, but improved knowledge and calculational treatments of the applicable phenomenology would be desirable.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5981618
• Report Number(s): LA-UR--79-2340; CONF-790816-38
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
97 MATHEMATICS AND COMPUTING
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
CRITICALITY
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
Nuclear Criticality Safety Program (NCSP)
REACTIVITY WORTHS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
Recriticality
SAFETY
SIMMER-II Code