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.2013.08.046Additional 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.