Published 1990 | Version v1
Book Metadata-only

Analysis of thermal mixing in the upper plenum of High Temperature engineering Test Reactor (HTTR)

Creators

  • 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

Description

The thermal mixing behavior in the upper plenum of the High Temperature engineering Test Reactor (HTTR) was investigated by the thermal-hydraulic analysis code STREAM. This code is vectrized so that a large and complicated system can be treated. Taking into consideration that there are many structures in the upper plenum and coolants with different temperature flow into the core being mixed in the upper plenum, a three-dimensional calculation was carried out to quantify the magnitude in thermal mixing in the upper plenum and a mesh effect and magnitude of thermal mixing were clarified. (author)

Additional details

Publishing Information

Publisher
Nuclear Energy Data Center.
Imprint Place
Tokai, Ibaraki (Japan)
Imprint Title
Proceedings of the first international conference on supercomputing in nuclear applications (SNA '90)
Imprint Pagination
689 p.
Journal Page Range
p. 92-97.

Conference

Title
1. international conference on supercomputing in nuclear applications.
Dates
12-16 Mar 1990.
Place
Mito (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
22035059
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COOLANTS; FLOW MODELS; GAS FLOW; HELIUM; HTTR REACTOR; HYDRAULICS; NUMERICAL SOLUTION; PRESSURE VESSELS; S CODES; TEMPERATURE DISTRIBUTION; THERMODYNAMICS; THREE-DIMENSIONAL CALCULATIONS; VECTOR PROCESSING
Descriptors DEC
COMPUTER CODES; CONTAINERS; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUID FLOW; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATHEMATICAL MODELS; NONMETALS; PROGRAMMING; RARE GASES; REACTORS; RESEARCH AND TEST REACTORS