Accident Progression for a Loss of Heat Sink with Scram in a LMFBR

机译：LmFBR中使用scram导致散热器损失的事故进展

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A description of a slow core meltdown in a liquid metal fast breeder reactor is presented for the conditions of loss-of-heat-sink following neutronic shutdown. Simple models are developed for the prediction of phase changes and/or relocation of the core materials including fuel, clad, ducts, control rod absorber material (B sub 4 C), and plenum gases. The sequence of events is accounted for and the accident progression is described up to the point of recriticality. The neutronic behavior of the disrupted core is analyzed in R-Z geometry with a static transport theory code (TWOTRAN). For most scenarios assessed, the reactor is expected to become recritical although large ramp rates are not anticipated. (ERA citation 04:023148)

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Bari, R. A.; Ludewig, H.; Pratt, W. T.; Sun, Y. H.;
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年度 1978
页码 1-74
总页数 74
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Lmfbr type reactors ; Meltdown ; Mathematical models ; Reactivity ; Scram;

机译：Lmfbr型反应器;熔化;数学模型;反应性; scram;

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3. TRANSIENT ANALYSIS OF DEPRESSURIZED LOSS-OF-FORCED-CIRCULATION ACCIDENT WITHOUT SCRAM IN HIGH-TEMPERATURE GAS-COOLED REACTOR [J] . HIROYUKI SATO, XING L. YAN, YUKIO TACHIBANA, Nuclear Technology . 2014,第3期

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4. DEVELOPMENT AND APPLICATION OF THE NEUTRONICS/THERMAL-HYDRAULICS COUPLING CODE FOR SAFETY ANALYSIS OF EBR-Ⅱ LOSS OF HEAT SINK TESTS WITHOUT SCRAM [C] . Daogang Lu, Chao Guo, Danting Sui International conference on nuclear engineering . 2016

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7. Uncertainty in unprotected loss-of-heat-sink, loss-of-flow, and transient-overpower accidents. [O] . Morris, E. E., Division, Nuclear Engineering 2007

机译：无保护的散热损失，流量损失和瞬态过载事故的不确定性。
8. Assessment of the Loss-of-Heat-Sink Accident with Scram in the LMFBR [R] . Bari, R. A., Ludewig, H., Pratt, W. T., 1978

机译：用LmFBR中的scram评估散热器泄漏事故

Accident Progression for a Loss of Heat Sink with Scram in a LMFBR

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