Published 1997
| Version v1
Miscellaneous
A systems approach to the scaling analysis of integral test results
Creators
- 1. Lockheed Martin Idaho Technologies, Idaho National Engineering Laboratory (United States)
Description
New nuclear reactor thermohydraulic designs, with passive safety features, pose new challenges to their computer simulation and analyses, the design of integral test facilities to represent them, and to the proper interpretation of the data from these facilities. A rigorous and systematic, eight-step methodology, was developed to scale and interpret the results from three different integral test facilities, and to relate them to the full scale plant. The methodology is not restricted to advanced reactors, or even reactors; it can be applied to other realms of engineering where complex processes and time-varying systems are involved
Additional details
Publishing Information
- Imprint Title
- Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety
- Imprint Pagination
- 1493 p.
- Journal Page Range
- p. Q3.1-Q3.7
Conference
- Title
- 5. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 14-18 Apr 1997
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 29048851
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTER-AIDED DESIGN; COMPUTERIZED SIMULATION; CONTAINMENT; CONTAINMENT SYSTEMS; DESIGN; FLOW RATE; HEAT TRANSFER; HYDRAULICS; NATURAL CONVECTION; PWR TYPE REACTORS; SYSTEMS ANALYSIS; TEST FACILITIES
- Descriptors DEC
- CONTAINMENT; CONVECTION; DESIGN; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT TRANSFER; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS