Published 1992
| Version v1
Journal article
Thermal hydraulics in a passively safe reactor
Creators
- 1. Kobe Univ. of Mercantile Marine (Japan)
- 2. Japan Atomic Energy Research Institute, Ibaraki-ken (Japan)
Description
In the advanced marine reactor that is being developed in Japan, decay heat accumulated in a reactor vessel will be released to the atmosphere through naturally circulating water in a container vessel. The authors are conducting studies on the heat transfer and fluid flow in a rectangular parallelpiped vessel equipped with a heater and a cooler to simulate the container vessel. The purpose of this paper is to investigate the effect of the geometric configuration, such as locations of the heater and the cooler and existence of the baffle plate, on the heat transfer performance
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 66
- Journal Page Range
- p. 596-597.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- past, present, and future.
- Acronym
- Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
- Dates
- 15-20 Nov 1992.
- Place
- Chicago, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24051020
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; FLUID FLOW; HEAT TRANSFER; HYDRAULICS; JAPAN; NATURAL CONVECTION; PRESSURE VESSELS; PROPULSION REACTORS; REACTOR SAFETY; RESEARCH PROGRAMS; TESTING; THERMAL ANALYSIS
- Descriptors DEC
- ASIA; CONTAINERS; CONVECTION; DEVELOPED COUNTRIES; ENERGY TRANSFER; POWER REACTORS; REACTORS; REMOVAL; SAFETY
Optional Information
- Secondary number(s)
- CONF-921102--.