Published November 2018 | Version v1
Journal article

Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor

  • 1. Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka Nishi-ku, Fukuoka-shi, Fukuoka, 319-0395 (Japan)
  • 2. Department of Advanced Energy Engineering Science, Kyushu University, 6-1 Kasugakouen Kasuga-shi Fukuoka, 816-0811 (Japan)
  • 3. Department of Electrical and Electrtonic Engineering, Kindai University, 3-4-1 Kowakae, HigashiOsaka city Osaka, 577-0818 (Japan)
  • 4. Japan Atomic Energy Agency, 4002 Narita-cho Oarai-machi Higashi-Ibaraki-gun, Ibaraki, 311-1393 (Japan)

Description

Highlights: • Tritium production using high temperature gas-cooled reactor (HTGR) is considered. • An irradiation test on High Temperature engineering Test Reactor (HTTR) is assumed. • The Li rod suited to the HTTR and produces 30 g of tritium in a year was designed. • The scenario of the irradiation test to confirm the Li rod performance was presented. • Li rod irradiation test to demonstrate the tritium production in the HTGR was proposed. - Abstract: Large quantities of tritium are required to start up fusion reactors and conducts engineering tests using tritium for a fusion blanket system. However, tritium is very rare and kg orders of tritium must be produced artificially. Tritium production, by 6Li(n,α)T reaction using a high temperature gas-cooled reactor (HTGR) has been proposed. This method considers the loading of Li rods into burnable poison holes in the HTGR. In this paper, the Li rod suited for use in the High Temperature engineering Test Reactor (HTTR) was designed, and tritium production and leakage from Li-rod capsules were evaluated by adjusting the thicknesses of LiAlO2, alumina, and Zr layers. An irradiation test scenario to be conducted in the HTTR for demonstration of the Li rod's tritium production and containment performance was presented.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2018.03.029

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2018.03.029;
PII
S0920379618302394;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
136
Journal Issue
Part A
Journal Page Range
p. 587-591
ISSN
0920-3796
CODEN
FEDEEE

Optional Information

Notes
© 2018 Elsevier B.V. All rights reserved.