Published January 10, 2014 | Version v1
Journal article

Research on the leak-rate characteristics of leak-before-break (LBB) in pressurized water reactor (PWR)

Description

Leak rate calculation is the foundation of Leak-Before-Break (LBB) technology application in Pressurized Water Reactor (PWR). In the paper, a leak rate Mathcad calculation code with different critical flow mathematical assumptions was completed. The code calculation results were contrasted from the published experimental data. The compared results show that the code calculation results are coincident with experimental data. However, the theoretical results are greater than experimental data with different crack L/D, stagnation pressures and subcooled temperatures in case of ignoring friction effect. While the crack friction effect is considered, the calculated results are well in accordance with the experimental data. Also, the different pressure drops are obtained and studied with variations of important parameters in detail. It demonstrates that the friction effect is a significant factor and must be considered in the crack leak rate calculation. The Mathcad code can be used to calculate the crack leak rate and provide application foundation of LBB in PWR pipe system. -- Highlights: • The leak rate mathematical models of LBB were studied and modified. • Mathcad programming of leak rate calculation and comparing with experimental data. • Studies of different initial conditions and friction effect. • Formed Mathcad code can be used to calculate the crack leak rate accurately

Availability note (English)

Available from http://dx.doi.org/10.1016/j.applthermaleng.2013.08.046

Additional details

Identifiers

DOI
10.1016/j.applthermaleng.2013.08.046;
PII
S1359-4311(13)00632-7;

Publishing Information

Journal Title
Applied Thermal Engineering
Journal Volume
62
Journal Issue
1
Journal Page Range
p. 133-140
ISSN
1359-4311
CODEN
ATENFT

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
45052661
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
COMPARATIVE EVALUATIONS; CRACKS; CRITICAL FLOW; EXPERIMENTAL DATA; FRICTION; MATHEMATICAL MODELS; PRESSURE DROP; PWR TYPE REACTORS
Descriptors DEC
DATA; ENRICHED URANIUM REACTORS; EVALUATION; FLUID FLOW; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Copyright
Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.