Development plan of high burnup fuel for high temperature gas-cooled reactors in future

被引:11
作者
Aihara, Jun [1 ]
Ueta, Shohei [1 ]
Honda, Masaki [2 ]
Blynskiy, Petr [3 ]
Gizatulin, Shamil [3 ]
Sakaba, Nariaki [1 ]
Tachibana, Yukio [1 ]
机构
[1] Japan Atom Energy Agcy, Oarai Res & Dev Ctr, Oarai, Ibaraki 3111393, Japan
[2] Nucl Fuel Ind Ltd NFI, Tokai Works, Tokai, Ibaraki 3191196, Japan
[3] Inst Nucl Phys, Alma Ata 050032, Kazakhstan
关键词
HTTR; coated fuel particle; nuclear/thermal design; sleeveless fuel rod; GTHTR300; HTR50S; irradiation test; packing fraction; high temperature gas-cooled reactor; fuel compact; RESEARCH-AND-DEVELOPMENT; BEHAVIOR; PARTICLE;
D O I
10.1080/00223131.2014.924886
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Plan and status of research and development (R&D) were described on coated fuel particle (CFP) and fuel compacts for the core of small-sized high-temperature gas-cooled reactor (HTGR) HTR50S at second step of phase I (second core of HTR50S). Specifications of existing CFPs for high burnup (HTR50S2-type-CFPs) were adopted as specifications of CFPs, to reduce R&D. HTR50S2-type-CFPs were fabricated based on technology developed in High Temperature Engineering Test Reactor (HTTR) project. The first irradiation test of HTR50S2-type-CFPs is now being carried out. In addition, R&D for fuel compact with high packing fraction is planned, because volume fraction of UO2 kernel to whole of HTR50S2-type-CFP is rather smaller than that of the HTTR-type-CFP. We would aim to complete the proof of nuclear/thermal design of second core of HTR50S on integrity of fuel, feeding back results of R&Ds and nuclear/thermal design to each other. In addition, we describe outline of R&D plans for core of HTR50S in phase II and practical HTGR in Japan in future, naturally safe HTGR.
引用
收藏
页码:1355 / 1363
页数:9
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