Fission product decay heat for thermal reactors
Description
In the past five years there have been new experimental programs to measure decay heat (i.e., time dependent beta- plus gamma-ray energy release rates from the decay of fission products) following thermal-neutron fission of 235U, 239Pu, and 241Pu for times after fission between 1 and approx. 105 sec. Experimental results from the ORNL program stress the very short times following fission, particularly in the first few hundred sec. Complementing the experimental effort, computer codes have been developed for the computation of decay heat by summation of calculated individual energies released by each one of the fission products. By suitably combining the results of the summation calculations with the recent experimental results, a new Decay Heat Standard has been developed for application to safety analysis of operations of light water reactors. The new standard indicates somewhat smaller energy release rates than those being used at present, and the overall uncertainties assigned to the new standard are much smaller than those being used at present
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
11552385.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- CONF-791058--71
Conference
- Title
- International conference on nuclear cross sections for technology.
- Dates
- 22 - 26 Oct 1979.
- Place
- Knoxville, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11552385
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; FISSION PRODUCTS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; ISOTOPES; RADIOACTIVE MATERIALS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS