Reflection of gamma radiation in a spherical concrete-walled room
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6818916
A correlation of the in-containment monitor reading and airborne radioactivity within containment is useful in assessing radiological consequences of postulated power plant accidents. One accident of concern in the loss-of-coolant accident. A design-basis release from the core to the containment can be postulated and a time-dependent in-containment monitor response due to direct radiation can then be calculated using a fast-running point kernel code, but this calculation provides no estimate of wall-scattered radiation. The question presently addressed is the following: Is the wall-scattered radiation of sufficient importance to preclude use of the point-kernel method in this calculation. This study shows that a point kernel code can be used to calculate in-containment dose rates with errors of <30%.
- Research Organization:
- Sargent and Lundy, Chicago, IL
- OSTI ID:
- 6818916
- Report Number(s):
- CONF-861102-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 53
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CALCULATION METHODS
CONTAINMENT
CONTAINMENT SYSTEMS
DOSES
ENGINEERED SAFETY SYSTEMS
HAZARDS
HEALTH HAZARDS
LOSS OF COOLANT
MONITORING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
RADIATION DOSES
RADIATION HAZARDS
RADIATION MONITORING
RADIATION PROTECTION
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
THERMAL POWER PLANTS
TIME DEPENDENCE
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CALCULATION METHODS
CONTAINMENT
CONTAINMENT SYSTEMS
DOSES
ENGINEERED SAFETY SYSTEMS
HAZARDS
HEALTH HAZARDS
LOSS OF COOLANT
MONITORING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
RADIATION DOSES
RADIATION HAZARDS
RADIATION MONITORING
RADIATION PROTECTION
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
THERMAL POWER PLANTS
TIME DEPENDENCE