Accident Analysis Model for Evaluation of Criticality Safety of CH-TRU Waste Shipping Casks
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:7036486
One of the main objectives in the safety analysis of a proposed type B radioactive material shipping cask is to demonstrate that the fully loaded cask will remain subcritical during any normal or hypothetical accident condition. Numerous computer codes can be used to determine the effective multiplication factor of the system; however, the crucial aspect of the criticality safety analysis lies in the development of a correct input data for the codes. This paper presents an accident analysis model developed for contract-handled transuranic (CH-TRU) waste casks, which can be adapted to any shipping cask configuration or capacity. The algorithm for the accident analysis model presented in this paper is a summary of the GEODENS-accident model GEOmetry and region atomic DENSity-computer code.
- Research Organization:
- University of New Mexico, Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 7036486
- Report Number(s):
- CONF-920606--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 65
- Country of Publication:
- United States
- Language:
- English
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