Published June 1991 | Version v1
Journal article

Development of statistical core thermal design methodology using a modified latin hypercube method

  • 1. Korea Inst. of Nuclear Safety, P.O. Box 16, Daeduk Danji, Taejon (Korea, Republic of)
  • 2. Korea Advanced Inst. of Science and Technology, P.O. Box 150, Cheongryang, Seoul (Korea, Republic of)

Description

This paper presents a statistical core thermal design methodology for generating the limit departure from nucleate boiling ratio (DNBR) and is used in assessing the best-estimate thermal margin in a reactor core. This new methodology adopts a modified Latin hypercube sampling method. In this method, the independencies of the input variables are verified through a correlation coefficient test for statistical treatment of their uncertainties. Next the DNBR response distribution is determined through a goodness-of-fit test. Finally, a limit DNBR with a one-sided 95% probability and a confidence level of 0.95 is estimated. This methodology is simpler than the conventional statistical method using the response surface and Monte Carlo simulation technique, but it maintains the same level of confidence in the limit DNBR result. From this study, it is deduced that the proposed methodology is useful for design application

Additional details

Publishing Information

Journal Title
Nuclear Technology
Journal Volume
94
Journal Issue
3
Series
Nucl. Technol.
Journal Page Range
407-415
ISSN
0029-5450
CODEN
NUTYB

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23011801
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S71: CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS;
Descriptors DEI
DESIGN; MONTE CARLO METHOD; REACTOR CORES; RESPONSE FUNCTIONS; SAMPLING; STATISTICAL MECHANICS; SURFACES
Descriptors DEC
FUNCTIONS; MECHANICS; REACTOR COMPONENTS