Published 1977
| Version v1
Report
Status and future needs of core melt down accident research
Creators
- 1. Hannover Univ., Inst. fuer Verfahrenstechnik der Technischen (Germany)
Description
This paper gives a summary of the German core meltdown research program. The most important activities of this program are described shortly, e.g. the development of a meltdown code, the investigation of the thermal-hydraulic behavior in a pool of molten core material, the analysis of the interaction between molten core material and concrete, an estimate of the general progress of the whole core meltdown accident by an energy balance and a determination of the physical and chemical properties of the core material. Additionally the questions still unanswered are enumerated
Additional details
Publishing Information
- Imprint Title
- Proceedings of a specialist meeting on the behaviour of water reactor fuel elements under accident conditions
- Imprint Pagination
- 774 p.
- Journal Page Range
- p. 224-257
- Report number
- NEA-CSNI-R--1977-13
Conference
- Title
- Specialist meeting on the behaviour of water reactor fuel elements under accident conditions
- Dates
- 13-16 Sep 1976
- Place
- Spaatind (Norway)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 42006199
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHEMICAL PROPERTIES; COMPUTER CODES; CONCRETES; CORIUM; ENERGY BALANCE; FEDERAL REPUBLIC OF GERMANY; FUEL RODS; MELTDOWN; NEA; PHYSICAL PROPERTIES; REACTOR ACCIDENT SIMULATION; REACTOR MATERIALS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; SYSTEM FAILURE ANALYSIS; THERMAL HYDRAULICS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; DEVELOPED COUNTRIES; EUROPE; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; INTERNATIONAL ORGANIZATIONS; MATERIALS; MECHANICS; OECD; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; SYSTEMS ANALYSIS; WESTERN EUROPE
Optional Information
- Notes
- 24 refs.