Published 1992 | Version v1
Journal article

Thermal hydraulics in a passively safe reactor

  • 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--.