Published 1991 | Version v1
Book

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).

Optional Information

Notes
Imprint:Composed of two volumes.