Evaluation of surge line thermal stratification and implementation to piping design
Creators
- 1. Korea Atomic Energy Research Inst., Daejon (Korea, Republic of)
- 2. ABB Combustion Engineering Co., Windsor, CT (United States)
Description
Recent observations at operating plants and subsequent U.S.NRC requirements have identified flow stratification in surge lines as a phenomenon that must be considered in the design basis of surge lines. During YGN Unit 3 pre-core hot functional testing, surge line pipe wall temperatures and pipe displacements were measured to determine the degree of surge line flow stratification. Test data from YGN Unit 3 indicate that stratified flow exists in the surge line during both heatup and cooldown. The measured displacements and temperatures were extensively reviewed and evaluated in detail: to verify the adequacy of thermal hydraulic model used to predict the pipe top-to bottom temperature differentials; to analytically correlate measured surge line temperatures and displacements; and to confirm the validity of the stratified flow analysis procedure. The generic nature of the thermal loading on the surge line as well as the correlation between the measured data and plant operations observed during surge line stratified flow test are also discussed. (author). 6 refs., 13 figs., 2 tabs
Additional details
Publishing Information
- Publisher
- Editora de Universidade Federal do Rio Grande do Sul.
- Imprint Place
- Porto Alegre, RS (Brazil)
- ISBN
- 85-7025-350-8
- Imprint Title
- Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 2
- Imprint Pagination
- 897 p.
- Journal Page Range
- p. 127-135.
Conference
- Title
- 13. International Conference on Structural Mechanics in Reactor Technology.
- Dates
- 13-18 Aug 1995.
- Place
- Porto Alegre, RS (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28001722
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEFORMATION; DYNAMIC LOADS; FINITE ELEMENT METHOD; MECHANICAL PROPERTIES; PIPES; PRESSURIZERS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR TECHNOLOGY; REACTORS; S CODES; STATIC LOADS; STRESS ANALYSIS; STRESSES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; COOLING SYSTEMS; NUMERICAL SOLUTION; SAFETY
Optional Information
- Notes
- Imprint:Conference organized by the International Association for Structural Mechanics in Reactor Technology and Universidade Federal do Rio Grande do Sul.