Published 1993 | Version v1
Book Metadata-only

Development of containment vessel for High Temperature Test Reactor

Creators

  • 1. Mitsubishi Heavy Industries, Ltd., Nagasaki (Japan). Nagasaki Shipyard and Machinery Works
  • 2. Mitsubishi Heavy Industries, Ltd., Nagasaki (Japan)
  • 3. Japan Atomic Energy Research Inst., Ibaraki (Japan)

Description

The results of a study on the strength the containment vessel of the HTTR subjected to internal pressure are shown together with the results of the elastic-plastic analysis and the structural model test. The point is the evaluation of the strength of knuckle and the influence of the non-axisymmetrically-located hatch on the upper head. The shape of the upper head is determined so that the upper head has higher strength than the cylinder part. As a result of the elastic-plastic analysis and the structural model test, it is confirmed that the upper head can bear the higher pressure than the cylinder and also the existence of non-axisymmetric hatch doesn't weaken the upper head

Part of:
2nd ASME-JSME international conference on nuclear engineering -- 1993

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers (ASME).
Imprint Place
New York, NY (United States)
ISBN
0-7918-0637-5
Imprint Title
2nd ASME-JSME international conference on nuclear engineering -- 1993
Imprint Pagination
914 p.
Journal Page Range
p. 841-846.

Conference

Title
2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
Dates
21-24 Mar 1993.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25058976
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
CONTAINMENT SYSTEMS; DESIGN; EXPERIMENTAL DATA; HTTR REACTOR; RELIABILITY; SYSTEMS ANALYSIS; THEORETICAL DATA
Descriptors DEC
CONTAINMENT; DATA; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INFORMATION; NUMERICAL DATA; REACTORS; RESEARCH AND TEST REACTORS

Optional Information

Secondary number(s)
CONF-930352--.