Study of fabrication of SiC-matrixed fuel compact for HTGR

Kawano, Takahiro*; Mizuta, Naoki; Ueta, Shohei; Tachibana, Yukio; Yoshida, Katsumi*

JAEA-Technology 2023-014, 37 Pages, 2023/08

JAEA-Technology-2023-014.pdf:2.35MB

Fuel compact for High Temperature Gas-cooled Reactor (HTGR) is fabricated by calcinating a matrix consisting of graphite and binder with the coated fuel particle. The SiC-matrixed fuel compact uses a new matrix made of silicon carbide (SiC) replacing the conventional graphite. Applying the SiC-matrixed fuel compact for HTGRs is expected to improve their performance such as power densities. In this study, the sintering conditions for applying SiC as the matrix of fuel compacts for HTGR are selected, and the density and thermal conductivity of the prototype SiC are measured.

Activity report of the research committee on fuel debris, 3-1; Current status and issues of the fuel debris characterization

Takano, Masahide; Miwa, Shuhei; Kawano, Shohei*

no journal, , 

This presentation gives the current status and issues of the fuel debris characterization and FP source term during severe accidents, as the activity report of the research committee on fuel debris of the Atomic Energy Society of Japan actioned in FY 2016-2017.

Criticality control technique development for Fukushima Daiichi fuel debris, 55; Evaluation for the drying behavior of fuel debris covered with water glass based neutron absorber

Suzuki, Seiya; Arai, Yoichi; Okamura, Nobuo; Watanabe, Masayuki; Kawano, Shohei*; Kawarada, Yoshiyuki*

no journal, , 

The water glass type neutron absorber has been developed as a measure to precaution of re-criticality during fuel debris retrieval. Since the neutron absorber covers the surface of the fuel debris, the drying of the water content of the fuel debris was suggested to be hindered. The drying test using the mock test piece was carried out in order to evaluate the effect on the drying behavior when the surface of the fuel debris is covered with the neutron absorber. We investigate the drying characteristic curve of the mock test piece by thermogravimetric analysis, and report the evaluation of drying behavior.

Criticality control technique development for Fukushima Daiichi fuel debris, 56; Study on scale effect the drying behavior of fuel debris covered with water glass based neutron absorber

Suzuki, Seiya; Arai, Yoichi; Watanabe, Masayuki; Kawano, Shohei*; Kawaharada, Yoshiyuki*

no journal, , 

The water glass type neutron absorber has been developed as a measure to precaution of re-criticality during fuel debris retrieval at the Fukushima Daiichi Nuclear Power Plant. The drying test using the mock test piece was carried out in order to evaluate the effect on the drying behavior. In this report, the scale-up tests was shown.