HTGR Knowledge Base
Conference Article: Research on irradiation behavior of VHTR fuel
Ikawa, K.; Fukuda, K.; Iwamoto, K. (Department of Fuels and Materials Research, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken (Japan))Abstract
The multipurpose VHTR being developed by JAERI will use TRISO-coated low enriched UO2> particles in the form of hollow cylinder called fuel compact. The dimension of the particle and the compact are shown in Table 1. Compacts are encased in a graphite sleeve to complete a fuel rod. Design target conditions for the fuel are 1350 deg. C, 2% FIMA and 7x1020 n/cm2 (E > 0.18MeV). Irradiation tests of the fuel have been performed in JMTR using a gas loop, sweep-gas capsules and closed capsules. The purpose of the present paper is to review the current status of these irradiation tests
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key words: Gas Cooled Reactor, Nuclear Technology
- Reference:
- Specialists' meeting on gas-cooled reactor fuel development
and spent fuel treatment Moscow (Russian Federation) 18-21
Oct 1983
- International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria); State Committee on the Utilisation of Atomic Energy of the USSR, Moscow (Russian Federation)
- IWGGCR--8, pp:201-211
- International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria); State Committee on the Utilisation of Atomic Energy of the USSR, Moscow (Russian Federation)