MCR Safety Dose Assessment in LOCA Condition of Westinghouse Type NPP
- 1. Korea Hydro and Nuclear Power Central Research Institute, Daejeon (Korea, Republic of)
Description
The MCR(Main Control Room) dose assessment is performed assuming LOCA(Loss Of Coolant Accident) which is the most limiting design basis accident and assumes the largest fission product release to the containment. For MCR dose assessment, some input parameters are needed. They are onsite atmospheric dispersion factor, accumulated break flow from each break point, initial condition for LOCA and etc. In this paper, ARCON96, RADTRAD and SCALE6.1 are used as analysis tools. This requirement is originated from TMI accident issue and the lesson. In 2003, the additional requirement is published by GL 2003-01. According to the documents, the additional requirement is the experimental data acquisition and the data check for the criteria of MCR habitability from MCR leakage test. MCR dose assessment is carried out by calculations of onsite dispersion factor, LOCA fission products release analysis and dose conversion factors. From this study, we find some conclusions as below: a. X/Q value at the early part of the accident has significant effect on MCR dose results b. Atmospheric stability is important factor that affects the X/Q. c. Categories (E~G) of atmosphere stability are the key factor in the case of X/Q value increase. d. FGR13/ICRP72 is more conservative than FGR11/12. From these conclusions we can find what major elements of MCR dose in LOCA could be considered to increase the safety margin.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Fall Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [3 p.]
Conference
- Title
- 2018 Fall Meeting of the KNS
- Dates
- 24-26 Oct 2018
- Place
- Yeosu (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50060449
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- CONTAINMENT; CONTROL ROOMS; DESIGN; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; LOSS OF COOLANT; SAFETY; SAFETY MARGINS; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- ACCIDENTS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs, 1 fig, 6 tabs