An improvement of estimation method of source term to the environment for interfacing system LOCA for typical PWR using MELCOR code
Creators
- 1. Risk and Environmental Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Interfacing-system loss-of-coolant-accident (ISLOCA) has been identified as the most hazardous accident scenario in the typical PWR plants. The present study as an effort to improve the knowledge of the source term to the environment during ISLOCA focuses on an improvement of the estimation method. The improvement was performed to take into account an effect of broken pipeline and auxiliary building structures relevant to ISLOCA. An estimation of the source term to the environment was for the OPR-1000 plants by MELOCR code version 1.8.6. The key features of the source term showed that the massive amount of fission products departed from the beginning of core degradation to the vessel breach. The release amount of fission products may be affected by the broken pipeline and the auxiliary building structure associated with release pathway
Additional details
Publishing Information
- Journal Title
- Journal of Radiation Protection and Research (2016)
- Journal Volume
- 42
- Journal Issue
- 2
- Series
- 7 refs, 10 figs, 2 tabs
- Journal Page Range
- p. 106-113
- ISSN
- 2508-1888
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 48082028
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FISSION PRODUCT RELEASE; INTERFACES; LOSS OF COOLANT; M CODES; PIPELINES; PWR TYPE REACTORS; SOURCE TERMS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS