Thermal transient analysis for structural integrity of high temperature components in HTTR
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Description
The High Temperature Engineering Test Reactor (HTTR) is the first reactor of graphite-moderated and helium gas-cooled type in Japan and it generates thermal energy at a very high temperature of 950degC at the reactor outlet. Since experience is very limited in evaluating the structural integrity for such a high temperature reactor, a reliable method is required to be established for analyzing transient responses of the reactor, particularly its thermal transient response. Such a method should provide criteria for classifying transient events into some loading categories, selecting representative transient events for each loading category and establishing analytical conditions and an analytical model for the events and also an analytical tool. This paper presents a method for analyzing thermal transient response of the HTTR reactor cooling system for representative events which are required for the structural integrity evaluation and also their analytical results. The analytical results could demonstrate unique features of the HTTR and its highly inherent safety. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- The 1st JSME/ASME joint international conference on nuclear engineering
- Imprint Pagination
- 1273 p.
- Journal Page Range
- v. 2 p. 291-298.
Conference
- Title
- 1. JSME/ASME joint international conference on nuclear engineering.
- Dates
- 4-7 Nov 1991.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23076071
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HTTR REACTOR; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RELIABILITY; SIMULATION; SYSTEMS ANALYSIS; THERMODYNAMICS; TRANSIENTS
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY
Optional Information
- Notes
- Imprint:Composed of two volumes.