Calculation of absorbed doses to water pools in severe accident sequences
Creators
- 1. Oak Ridge National Lab., TN (United States)
Description
A methodology is presented for calculating the radiation dose to a water pool from the decay of uniformly distributed nuclides in that pool. Motivated by the need to accurately model radiolysis reactions of iodine, direct application is made to fission product sources dissolved or suspended in containment sumps or pools during a severe nuclear reactor accident. Two methods of calculating gamma absorption are discussed - one based on point-kernal integration and the other based on Monte Carlo techniques. Using least-squares minimization, the computed results are used to obtain a correlation that relates absorbed dose to source energy and surface-to-volume ratio of the pool. This correlation is applied to most relevant fission product nuclides and used to actually calculate transient sump dose rate in a pressurized-water reactor (PWR) severe accident sequence
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI92005370; NTIS; INIS; GPO.Files
23035257.pdf
Files
(1.8 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 40 p.
- Report number
- NUREG/CR--5808
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23035257
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT; FISSION PRODUCT RELEASE; FISSION PRODUCTS; INTEGRALS; IODINE; MATHEMATICAL MODELS; MONTE CARLO METHOD; POINT KERNELS; PWR TYPE REACTORS; RADIATION ABSORPTION ANALYSIS; RADIATION DOSES; RADIATION EFFECTS; RADIATION TRANSPORT; REACTOR ACCIDENTS; REACTOR SAFETY; WATER RESERVOIRS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; CHEMICAL ANALYSIS; ELEMENTS; ENRICHED URANIUM REACTORS; HALOGENS; ISOTOPES; KERNELS; MATERIALS; NONDESTRUCTIVE ANALYSIS; NONMETALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTORS; SAFETY; SURFACE WATERS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- ORNL/TM--11970.