Present status of research on thermal hydraulic behavior in conventional light water reactors during severe accidents and in advanced light water reactors
Creators
- 1. Tsukuba Univ., Ibaraki (Japan). Inst. of Engineering Mechanics
Description
After having experienced TMI and Chernobyl nuclear power accidents, the importance of reactor containment vessels has become to be recognized anew. It is very important to grasp the thermal hydraulic behavior in the severe accidents that cause core damage. Atomic Energy Society of Japan organized the special committee on the investigation and research of the thermal hydraulic behavior in containment vessels in July, 1991. It was decided to investigate this problem related to severe accidents for three years. In this book, the results of the investigation carried out for three years are summarized. The thermal hydraulic flow in containment vessels at the time of severe accidents, the problems in the thermal hydraulic flow at the time of severe accidents such as the interaction of melted core with coolant and structural materials and others, the analysis codes for the thermal hydraulic flow in containment vessels at the time of severe accidents, and the design of new type containment vessels and statically safe reactors and the main problems are reported. (K.I.)
Additional details
Additional titles
- Original title (Japanese)
- Shibiaakushidento to shingata keisuiro no netsuryudo kyodo kenkyu no genjo
Publishing Information
- Publisher
- Atomic Energy Society of Japan, Tokyo (JP).
- Imprint Place
- Tokyo (Japan)
- Imprint Pagination
- 399 p.
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 26047581
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; BUILDING MATERIALS; BWR TYPE REACTORS; CONCRETES; COOLANTS; FISSION PRODUCT RELEASE; HEAT TRANSFER; HEATING; HYDRAULICS; HYDROGEN; LIQUID FLOW; M CODES; MELTDOWN; PLANNING; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR SAFETY; SAFETY ANALYSIS; T CODES; VAPOR CONDENSATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; MATERIALS; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS