Published August 1985
| Version v1
Journal article
Evaluation of fission product release rates during postulated core meltdown accidents
- 1. Hanyang Univ., Seoul (Republic of Korea)
Description
An investigation of fission product release rates under severe accident conditions is presented for a pressurized water reactor with a large dry containment. In the calculation of fission product source terms, the numerical scheme by using core node temperatures during heatup and meltdown is introduced and incorporated into the MARCH code. The results indicated that the significant differences between the numerical integration method and WASH-1400 method are observed, especially Ru and La release categories. (Author)
Additional details
Publishing Information
- Journal Title
- Res. Rep., Hanyang Res. Inst. Ind. Sci.
- Journal Volume
- 21
- Series
- Res. Rep., Hanyang Res. Inst. Ind. Sci.
- Journal Page Range
- 227-235
- CODEN
- RRHSD
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 18032698
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; FISSION PRODUCT RELEASE; M CODES; MELTDOWN; PWR TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS