Published 1986
| Version v1
Book
Analysis of ATWS type tests in the LV-400 facility using RELAP5/MOD1
- 1. Dipartimento di Energetica, Politecnico di Torino, C. so Duca Degli Abruzzi 24, 10129 Torino
Description
Experimental results of thermal-hydraulic transients carried out on the LV-400 test facility by modulating one single parameter at a time are presented. The modulated parameters are the test section power, the flow rate and the test section power, the flow rate and the test section inlet temperature. The reference transients are the ATWS and the initial steady rate conditions are typical of the three loop Westinghouse PWR, whose subchannel equivalent diameter and length are the same as the LV-400 test section. The response of the test facility to such transients has been analysed using the RELAP5/MODI computer code in order to validate the code against data from separate effect tests in a rather simple geometry
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-121-5
- Imprint Title
- Proceedings of the international ANS/ENS topical meeting on thermal reactor safety
- Journal Page Range
- p. 18.6.1-18.6.15.
Conference
- Title
- International ANS/ENS topical meeting on thermal reactor safety.
- Dates
- 2-6 Feb 1986.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18080579
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIMENSIONS; FLOW RATE; HYDRAULICS; POWER INPUT; PWR TYPE REACTORS; R CODES; REACTOR SAFETY EXPERIMENTS; RESPONSE FUNCTIONS; TEMPERATURE DEPENDENCE; TEST FACILITIES; THERMODYNAMICS; TRANSIENTS; VERIFICATION
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FUNCTIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS