Published May 2019 | Version v1
Miscellaneous

Study of SiC-matrix fuel element for HTGR

  • 1. Japan Atomic Energy Agency, Oarai, Ibaraki (Japan)

Description

Enhancement of safety and cooling performance of fuel elements are desired for a commercial High Temperature Gas-cooled Reactor (HTGR). Applying sleeveless fuel elements and dual side directly cooling structures with oxidation resistant SiC-matrix fuel compact has a possibility of improving safety and cooling performance at the pin-in-block type HTGR. The irradiated effective thermal conductivity of a fuel compact is an important physical property for core thermal design of the pin-in-block type HTGR. In order to discuss the irradiated effective thermal conductivity of the SiC-matrix fuel compact which could improve the cooling performance of the reactor, the maximum fuel temperature during normal operation of the pin-in-block type HTGR with dual side directly cooling structures are analytically evaluated. From these results, the desired irradiated thermal conductivity of SiC matrix are discussed. In addition, the suitable fabrication method of SiC-matrix fuel compact is examined from viewpoints of the sintering temperature, the purity and the mass productivity. (author)

Part of:
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)

Additional details

Publishing Information

Imprint Title
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)
Imprint Pagination
[4028 p.]
Journal Page Range
5 p.

Conference

Title
27. international conference on nuclear engineering
Acronym
ICONE-27
Dates
19-24 May 2019
Place
Tsukuba, Ibaraki (Japan)

Optional Information

Notes
Available as Internet Data in PDF format, Folder Name: Track05, Paper ID: ICONE27-2157F.pdf; 11 refs., 5 figs., 3 tabs.