Preliminary safety evaluation of the advanced burner test reactor.

Dunn, F. E. ; Fanning, T. H. ; Cahalan, J. E. ; Argonne National Laboratory. Nuclear Engineering Division.

Argonne National Laboratory

关键词: Radioactivity;    Pumping;    Burners;    Simulation;    Natural Convection;   

DOI  :  10.2172/924683
RP-ID  :  ANL-AFCI-172
RP-ID  :  DE-AC02-06CH11357
RP-ID  :  924683

美国|其它

来源: UNT Digital Library

【 摘 要 】

Results of a preliminary safety evaluation of the Advanced Burner Test Reactor (ABTR) pre-conceptual design are reported. The ABTR safety design approach is described. Traditional defense-in-depth design features are supplemented with passive safety performance characteristics that include natural circulation emergency decay heat removal and reactor power reduction by inherent reactivity feedbacks in accidents. ABTR safety performance in design-basis and beyond-design-basis accident sequences is estimated based on analyses. Modeling assumptions and input data for safety analyses are presented. Analysis results for simulation of simultaneous loss of coolant pumping power and normal heat rejection are presented and discussed, both for the case with reactor scram and the case without reactor scram. The analysis results indicate that the ABTR pre-conceptual design is capable of undergoing bounding design-basis and beyond-design-basis accidents without fuel cladding failures. The first line of defense for protection of the public against release of radioactivity in accidents remains intact with significant margin. A comparison and evaluation of general safety design criteria for the ABTR conceptual design phase are presented in an appendix. A second appendix presents SASSYS-1 computer code capabilities and modeling enhancements implemented for ABTR analyses.