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Conference Article: Capsule design, fabrication and irradiation for tensile creep test on HTGR graphites at 1200 deg. C in the JMTR

Saito, T. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Kikuchi, T.; Arai, T.; Ugachi, H. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)

Abstract

An irradiation creep test under uniaxial tension in JMTR has been performed by JAERI as one of the collaborative efforts on HTGR graphite development and testing with USDOE. The purpose of the test is to determine secondary creep coefficients at 1200 deg. C of isotropic IG-110 graphite and near-isotropic H-451 graphite. The irradiation capsule has withstood so far c.a. 1600 EFPH irradiation in JMTR. The paper describes the outline of the design, fabrication and operational progress of the capsule designated as Capsule 89M-6A. Thermal and structural designs were devised to achieve the good thermal insulation and the mechanical integrity of key components inside the capsule. Seven dogbone type tensile specimens were encapsulated together with other unstressed control specimens. The specimen temperature control system and load control system are similar to those utilized in the previous creep tests. In the course of three irradiation cycles in JMTR, the graphite specimens have been subjected to nearly constant temperatures and the specified tensile load. The capsule will be unloaded after another irradiation cycle.

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key words: creep; design; fabrication; graphite; htgr type reactors; irradiation capsules; irradiation; temperature range 1000-4000 k; tensile properties; carbon; gas cooled reactors; graphite moderated reactors
Reference:
Specialists' meeting on the status of graphite development for gas cooled reactors. Tokai, Ibaraki (Japan). 9-12 Sep 1991
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--690, pp:219-225