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JAEA Reports

Development of BDI behavior evaluation method in the fast reactor fuel assembly; Improvement of out-of-pile bundle compression test technology

Higashiuchi, Atsushi; Ishimi, Akihiro; Katsuyama, Kozo; Uwaba, Tomoyuki; Ichikawa, Shoichi

JAEA-Technology 2015-057, 72 Pages, 2016/03

JAEA-Technology-2015-057.pdf:36.91MB

Bundle-duct interaction (BDI) in fast reactors (FRs) is one of the limiting factors for burnup. To study the high performance fuel for FR fuel, it is important to establish the method to predict accurately the BDI behavior for the fuel assembly of large-diameter fuel pins. Therefore, it was adopted a new method that the bundle compression test apparatus is placed outside the cell, the bundle specimen is put in the airtight container for contamination prevention, and the bundle specimen is carried in the cell for internal observation by X-ray CT examination apparatus. From the result of this test, it was confirmed that the new method of out-of-pile bundle compression test is carried out as it was before. The results of this test are available to study integrity assessment of fast reactor fuel, validation of the BDI analysis code and substantiation of the safety design guidelines of fast reactor. In addition, it is possible to reflect in the BDI behavior evaluation for "ASTRID".

Oral presentation

BDI behavior evaluation of "Monju" advanced reactor and demonstration reactor, 2; The Result of out-of-pile bundle compressive test for a large diameter pin

Higashiuchi, Atsushi; Ishimi, Akihiro; Katsuyama, Kozo; Uwaba, Tomoyuki; Ichikawa, Shoichi

no journal, , 

no abstracts in English

Oral presentation

Development of remote decontamination techniques for reactor building, 8; Analysis of Concrete core sample from Operation Floor of Unit 2

Higashiuchi, Atsushi; Maeda, Koji; Otani, Akira; Sasaki, Shinji; Katsuyama, Kozo; Chigira, Takayuki*; Murata, Hirotoshi*

no journal, , 

no abstracts in English

Oral presentation

Development of remote decontamination techniques for reactor building, 2; Analysis of concrete core sample from south side floor of first floor in Unit 1

Higashiuchi, Atsushi; Maeda, Koji; Sasaki, Shinji; Katsuyama, Kozo; Otani, Akira; Chigira, Takayuki*; Murata, Hirotoshi*

no journal, , 

In the development of remote decontamination technology of the reactor building, we were carried out a detailed analysis of concrete samples (hereinafter referred to as "core sample") taken from TEPCO Fukushima Daiichi Nuclear Power Station (hereinafter referred to as "1F") Unit 1 reactor building first floor south side floor, etc..

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