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JAEA Reports

Survey and Research of Earthquake (XII)

Sasa, Koichi*

JNC TJ7400 2005-009, 145 Pages, 1996/03

JNC-TJ7400-2005-009.PDF:11.29MB

Committe's activities of 1995 fiscal year was not so different to these continnally obtained since the previous year, namely an accumulation and an analysis of the observed data on ground motion and underground water behavior caused by earthquake in the Omine area of the Kamaishi Mine in Iwate.

JAEA Reports

None

Sasa, Koichi*; *; *; *; *; Ishijima, Yoji*; *

PNC TJ1552 93-001, 243 Pages, 1993/03

PNC-TJ1552-93-001.pdf:7.19MB

None

JAEA Reports

None

Sasa, Koichi*; *; *; *; *; *; *

PNC TJ1552 91-001, 277 Pages, 1991/04

PNC-TJ1552-91-001.pdf:7.2MB

None

JAEA Reports

None

Sasa, Koichi*

PNC TN3720 90-019, 49 Pages, 1990/10

PNC-TN3720-90-019.pdf:4.95MB

None

JAEA Reports

None

Sasa, Koichi*

PNC TJ4552 90-001, 175 Pages, 1990/04

PNC-TJ4552-90-001.pdf:12.43MB

None

JAEA Reports

None

Sasa, Koichi*

PNC TJ7308 90-001, 87 Pages, 1990/03

PNC-TJ7308-90-001.pdf:2.49MB

None

JAEA Reports

None

Sasa, Koichi*; *; *

PNC TJ4552 89-002, 150 Pages, 1989/04

PNC-TJ4552-89-002.pdf:10.26MB

None

JAEA Reports

None

Sasa, Koichi*; *; *; 15 of others*

PNC TJ4552 88-001, 184 Pages, 1988/06

PNC-TJ4552-88-001.pdf:13.1MB

None

Oral presentation

Accident-Tolerant Fuel R&D Program in Japan

Yamashita, Shinichiro; Mohamad, A. B.; Ioka, Ikuo; Nemoto, Yoshiyuki; Kawanishi, Tomohiro; Kaji, Yoshiyuki; Osaka, Masahiko; Murakami, Nozomu*; Owaki, Masao*; Sasaki, Masana*; et al.

no journal, , 

Japan's Accident Tolerant Fuel (ATF) research and development (R&D) program has been conducted since 2015 in cooperation with power plant providers, fuel venders and universities for making the most use of the experiences in R&D, practical design, and evaluations of fuels and cores of commercial Light Water Reactors (LWRs). An overview of the present R&D progress is given, in relation to the role of Japan Atomic Energy Agency (JAEA) in the program. The ATF candidate materials currently under consideration are the following three claddings: the silicon carbide (SiC) composite which is potentially applicable for Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR), the FeCrAl steel strengthened by dispersion of fine oxide particles (FeCrAl-ODS) for BWR, and Cr-coated zircalloy claddings for PWR. In addition to the cladding materials, R&D on the SiC-made BWR channel box and accident tolerant control rods are also underway.

Oral presentation

Development of a portable sand filling device for manufacturing waste package for radioactive waste

Hayashi, Hirokazu; Nanri, Tomohiro; Hanzawa, Mamoru*; Sasaki, Yuki*; Torii, Kazuyuki*

no journal, , 

To prevent subsidence in a radioactive waste burial site, it is crucial to eliminate any harmful voids. To address this, a method utilizing a large shaking table to fill the voids in the container with sand has been developed. However, decommissioning facilities face constraints on installation space, making the use of a large shaking table challenging. Consequently, a portable sand filling device was developed, and both small-scale tests with a compact container and full-scale tests using a 200L drum were conducted. The test results confirmed a sand filling rate of 80% or more, indicating the feasibility of sand filling with the portable device.

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