Radioactive material release from a containment vessel during a fire accident
Conference
·
OSTI ID:1209013
- Savannah River Site (SRS), Aiken, SC (United States)
A methodology is presented to determine the source term for leaks and ruptures of pressurized vessels. The generic methodology is applied to a 9975 Primary Containment Vessel (PCV) which losses containment due to a hypothesized fire accident. The release due to a vessel rupture is approximately two orders of magnitude greater than the release due to a leak.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-AC09-08SR22470
- OSTI ID:
- 1209013
- Report Number(s):
- SRNS-STI-2015-00129
- Resource Relation:
- Conference: 2015 ASME Pressure Vessel and Piping Conference
- Country of Publication:
- United States
- Language:
- English
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