Published 1987
| Version v1
Journal article
Simulation of thermal mixing in main steam generator feedlines
Description
Thermal mixing in a representative model of a main feedwater line that carries feedwater to the steam generator and auxiliary feedwater injector is investigated using the TEM-PEST Version L Mod 4 computer code; a single-phase, three-dimensional, time-dependent, hydrothermal analysis code. Transient simulation was performed and the resultant temperature histories were examined in order to assess the degree of thermal mixing and its possible implications concerning pressurized thermal shock and thermal fatigue cracking phenomena. Under certain auxiliary feedwater injector flow rates, thermal stratification was predicted
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 55
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 737-739
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society winter meeting.
- Dates
- 15-19 Nov 1987.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20003737
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; CRACKS; FATIGUE; FEEDWATER; HYDRAULICS; PWR TYPE REACTORS; STEAM GENERATORS; STRATIFICATION; T CODES; THERMAL SHOCK; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE
- Descriptors DEC
- BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; MECHANICAL PROPERTIES; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTORS; SIMULATION; SOLVENTS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8711195--.