Beta and gamma dose calculations for PWR and BWR containments
Analyses of gamma and beta dose in selected regions in PWR and BWR containment buildings have been performed for a range of fission product releases from selected severe accidents. The objective of this study was to determine the radiation dose that safety-related equipment could experience during the selected severe accident sequences. The resulting dose calculations demonstrate the extent to which design basis accident qualified equipment could also be qualified for the severe accident environments. Surry was chosen as the representative PWR plant while Peach Bottom was selected to represent BWRs. Battelle Columbus Laboratory performed the source term release analyses. The AB epsilon scenario (an intermediate to large LOCA with failure to recover onsite or offsite electrical power) was selected as the base case Surry accident, and the AE scenario (a large break LOCA with one initiating event and a combination of failures in two emergency cooling systems) was selected as the base case Peach Bottom accident. Radionuclide release was bounded for both scenarios by including spray operation and arrested sequences as variations of the base scenarios. Sandia National Laboratories used the source terms to calculate dose to selected containment regions. Scenarios with sprays operational resulted in a total dose comparable to that (2.20 /times/ 10/sup 8/ rads) used in current equipment qualification testing. The base case scenarios resulted in some calculated doses roughly an order of magnitude above the current 2.20 /times/ 10/sup 8/ rad equipment qualification test region. 8 refs., 23 figs., 12 tabs.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5863143
- Report Number(s):
- NUREG/CR-5175; SAND-88-1605; ON: TI89016086
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
FISSION PRODUCT RELEASE
CONTAINMENT
PWR TYPE REACTORS
A CODES
BETA DOSIMETRY
GAMMA DOSIMETRY
GAMMA RADIATION
HEAT TRANSFER
HYDRAULICS
I CODES
P CODES
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
RADIATION DOSES
RADIOISOTOPES
REACTOR SAFETY
RECOMMENDATIONS
SOURCE TERMS
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
ACCIDENTS
COMPUTER CODES
DOSES
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ELECTROMAGNETIC RADIATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
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HTGR TYPE REACTORS
IONIZING RADIATIONS
ISOTOPES
MECHANICS
POWER REACTORS
RADIATIONS
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REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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