Assessment of irradiation temperature stability of the first irradiation test rig in the HTTR
Description
The High Temperature Engineering Test Reactor (HTTR) can provide very large irradiation spaces at high temperatures for various irradiation tests. The first irradiation test rig for the HTTR, the I-I type irradiation equipment, was developed for an in-pile creep test on a stainless steel with large standard size specimens. The equipment uses the ambient high temperature of the core for the irradiation temperature control. The target irradiation temperatures are 550 and 600 deg. C with the target temperature deviation of ±3 deg. C. In this study, the specimen temperature stability at the irradiation test was assessed by both analytical and experimental approaches. The irradiation temperature changes at transient conditions were analyzed by a finite element method (FEM) code and the temperature controllability of the equipment was examined by a mockup test. The controllability was evaluated with the measured temperature transient data at the core graphite components in the Rise-to-Power tests of the HTTR. The result indicates that the temperature control method of the I-I type irradiation equipment is effective to keep the irradiation temperature stable in the irradiation test.
Additional details
Identifiers
- PII
- S0029549303000414;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 223
- Journal Issue
- 2
- Journal Page Range
- p. 133-143
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Syrian Arab Republic
- INIS RN
- 43043205
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FINITE ELEMENT METHOD; HTTR REACTOR; IN PILE LOOPS; IRRADIATION; STAINLESS STEELS; TEMPERATURE CONTROL; TEMPERATURE RANGE 0400-1000 K; TEST FACILITIES; TESTING
- Descriptors DEC
- ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; CONTROL; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HIGH ALLOY STEELS; HTGR TYPE REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.
- Notes
- This record replaces 35001202