Published 1986
| Version v1
Book
Development of a two-dimensional core-wide heat-up code MUFLAR and its application to analysis of TMI-2 core damage behavior
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
A two-dimensional core-wide heat-up code MUFLAR has been developed, which calculates two-dimensional flow of steam-hydrogen mixture and radial heat transport by thermal radiation between fuel rod groups. Constitutive models are based on those verified through analyses of wide range of experiments. The code has been applied to an analysis of TMI-2 core damage behavior. The calculated results are in good agreement with the results of recent core examinations. The analysis indicates that cross flow has a radial averaging effect on core temperature. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Soc. of Japan.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of second international topical meeting on nuclear power plant thermal hydraulics and operations
- Imprint Pagination
- 1191 p.
- Journal Page Range
- p. 6/41-6/48.
Conference
- Title
- 2. international topical meeting on nuclear power plant thermal hydraulics and operations.
- Dates
- 15-17 Apr 1986.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 18061820
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FORCED CONVECTION; FUEL RODS; FUEL-COOLANT INTERACTIONS; HEAT TRANSFER; HYDROGEN; M CODES; MELTDOWN; NATURAL CONVECTION; NUMERICAL SOLUTION; REACTOR CORES; STEAM; THERMAL RADIATION; THREE MILE ISLAND-2 REACTOR; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONVECTION; ELECTROMAGNETIC RADIATION; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; NONMETALS; POWER REACTORS; PWR TYPE REACTORS; RADIATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS