The nuclear criticality analyses of the spent fuel pool under the postulated conditions of loss of spent fuel pool water and loss of neutron absorbers in the spent fuel racks, for Taipower’s Chinshan Nuclear Power Plant, were performed primarily using the Monte Carlo program MCNP5 in association with the deterministic neutron transport code CASMO-4. The results of these analyses can be used to help understand the impact of these beyond-design-basis accidents to the nuclear criticality, as well as facilitate nuclear utilities and regulatory bodies to develop the safety measures and regulations needed to prevent the criticality accidents.
- Nuclear Engineering Division
Nuclear Criticality Analyses of the Spent Fuel Pool Under Loss of Spent Fuel Pool Water and Neutron Absorbers in the Racks for Taipower’s Chinshan Nuclear Power Plant
- Views Icon Views
- Share Icon Share
- Search Site
Kuo, W. "Nuclear Criticality Analyses of the Spent Fuel Pool Under Loss of Spent Fuel Pool Water and Neutron Absorbers in the Racks for Taipower’s Chinshan Nuclear Power Plant." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering. Chengdu, China. July 29–August 2, 2013. V005T11A017. ASME. https://doi.org/10.1115/ICONE21-16578
Download citation file: