Safety study on nuclear heat utilization system - accident delineation and assessment on nuclear steelmaking pilot plant
Creators
- 1. Ishikawajima-Harima Heavy Industries Co., Ltd., Tokyo, Japan
Description
This paper presents accident delineation and assessment on a nuclear steelmaking pilot plant as an example of nuclear heat utilization systems. The reactor thermal energy from VHTR is transported to externally located chemical process plant employing helium-heated steam reformer by an intermediate heat transport loop. This paper on the nuclear steelmaking pilot plant will describe (1) system transients under accident conditions, (2) impact of explosion and fire on the nuclear reactor and the public and (3) radiation exposure on the public. The results presented in this paper will contribute considerably to understanding safety features of nuclear heat utilization system that employs the intermediate heat transport loop and the helium-heated steam reformer
Files
Additional details
Publishing Information
- Imprint Title
- Third Japan-US seminar on HTGR safety technology: proceedings. Volume I
- Journal Page Range
- p. 204-214.
- Report number
- NUREG/CP--0045-Vol.1
Conference
- Title
- 3. Japan/US HTGR safety technology seminar.
- Dates
- 2-3 Jun 1982.
- Place
- Upton, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15034150
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHEMICAL REACTIONS; EXPLOSIONS; FAILURE MODE ANALYSIS; FIRES; HAZARDS; HELIUM; PROCESS HEAT; RADIATION HAZARDS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RISK ANALYSIS; TRITIUM; USES; VHTR REACTOR
- Descriptors DEC
- ACCIDENTS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; COOLING SYSTEMS; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEALTH HAZARDS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; POWER REACTORS; RADIOISOTOPES; RARE GASES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; YEARS LIVING RADIOISOTOPES