Development of ceramic-coated lithium particles for tritium production tests in high temperature engineering test reactor
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Description
Ceramic-coated lithium particles (CCLP) are proposed for the tritium production tests in High Temperature Engineering Test Reactor (HTTR). The CCLP-production method and its tritium-retention as well as -release capability are mainly studied. The CCLP consists of a lithium compound kernel coated with ceramic layers. The kernel is made from lithium compound like LiAlO2. Ceramic materials like Al2O3 are used for the coating layers. The present study has made clear that tritium leakage from CCLP is less than 1% after 400-days-heating at 1,000K, and the tritium can be released completely in a short time by heating over 1,400K. From these characteristics, it is expected that the tritium can be well extracted from the CCLP by heating over 1,400K in the post irradiation test after irradiation under 1,000K in the HTTR. Furthermore, a good chemical stability between the kernel and coatings was confirmed through X-ray diffraction tests after heating of their powders. The mechanical integrity of coating layers for inner gas pressure in the CCLP was evaluated to be good on the basis of material data. (author)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.40.65Abstract (Japanese)
高温工学試験研究炉でのトリチウム製造試験に被覆リチウム粒子を用いることを提案し、この粒子のトリチウム保持特性を評価した。この粒子は、セラミックをリチウム化合物のカーネルに被覆したものであり、セラミック被覆にはAl2O3、カーネルにはLiAlO3等の物質を使用する。本検討より、1000Kで400日加熱しても、この粒子からのトリチウムの漏洩率は1%以下に押さえることができ、また、1400K以上で加熱すれば短時間でほぼ完全に放出できることが明らかとなった。この特性から、HTTRのトリチウム製造試験では1000K以下で照射し、照射後この粒子を1400K以上に加熱することにより容易にトリチウムを抽出できるものと考える。更に、この粒子を核融合炉に装荷しバッチ交換してトリチウムを製造すれば、ブランケット等のトリチウム漏洩防止機能への要求は低くなるものと考えられる。(日本)Additional details
Additional titles
- Original title (Japanese)
- 高温工学試験研究炉におけるトリチウム製造試験のための被覆リチウム粒子の開発
Identifiers
- DOI
- 10.3327/jaesj.40.65;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 40
- Journal Issue
- 1
- Journal Page Range
- p. 65-69
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54066658
- Subject category
- S36: MATERIALS SCIENCE; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- CERAMICS; COATED FUEL PARTICLES; EXTRACTION; FEASIBILITY STUDIES; HTTR REACTOR; LITHIUM COMPOUNDS; MECHANICAL PROPERTIES; PRODUCTION; STABILITY; TRITIUM
- Descriptors DEC
- ALKALI METAL COMPOUNDS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; REACTORS; RESEARCH AND TEST REACTORS; SEPARATION PROCESSES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- This record replaces 29025754