Published 1994 | Version v1
Miscellaneous

Assessment of two uncertainty quantification methods for source term analysis

  • 1. Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)
  • 2. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

Two methods of uncertainty quantification have been assessed for application to the source term analysis of Younggwang 3 and 4 using the MAAP 3.0B code. The two methods of uncertainty analysis, i.e., the response surface method and the Latin hypercube sampling method, produced slightly different results for the empirical distribution function of the CsI release fraction from the Younggwang reactor containment. In source term analysis, the response surface method has the relative merits in the importance and the sensitivity analyses: By this method, important qualitative information about the relation between the inputs and the outputs can be obtained. However, it is found that it is difficult to ascertain the accuracy of the response surface method. Also, when the approximate model is not suitable, the above advantages of the response surface method do not outweigh the loss in accuracy. In this case, the Latin hypercube method is superior to the response surface method: That is, the Latin Hypercube method is more readily executable without any prior procedure to obtain an approximate model

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
988 p.
Journal Page Range
p. 497-502

Conference

Title
1994 spring meeting of the KNS
Dates
27-28 May 1994
Place
Pohang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38022774
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CONTAINMENT; M CODES; SENSITIVITY ANALYSIS; SOURCE TERMS; YONGGWANG-3 REACTOR; YONGGWANG-4 REACTOR
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs, 2 figs, 4 tabs