Published October 2018 | Version v1
Miscellaneous

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.

Part of:
Proceedings of the KNS 2018 Fall Meeting

Additional details

Identifiers

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