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Journal Articles

SiC coating as hydrogen permeation reduction and oxidation resistance for nuclear fuel cladding

Usui, Takahiro*; Sawada, Akihiko; Amaya, Masaki; Suzuki, Akihiro*; Chikada, Takumi*; Terai, Takayuki*

Journal of Nuclear Science and Technology, 52(10), p.1318 - 1322, 2015/10

 Times Cited Count:48 Percentile:97.39(Nuclear Science & Technology)

SiC coating is one of countermeasures for the prevention of oxidation and hydrogen embrittlement of fuel claddings because SiC has high resistance of oxidation and hydrogen permeation. Hydrogen permeation and oxidation experiments for the cladding materials with SiC coatings were conducted in unirradiated conditions. The sputtering method was employed to make SiC coatings. In the hydrogen permeation experiment, SUS316 was used as a base material of the coating. SUS316 with SiC coatings showed hydrogen permeation reduction by one order of magnitude. In the oxidation experiments, Zry-4 and SUS316 were used as base materials of the coatings. The weight gain of the Zry-4 specimens with a SiC coating decreased by about one-fifth compared to the uncoated ones. This phenomenon was observed for SUS316 at 750 $$^{circ}$$C as well. The peel-off of the coating was observed in some experiments, and it is considered that the peel-off was caused by the difference of the thermal expansions between coatings and base materials. Thicker coatings showed better oxidation resistance, but thinner coatings showed more tolerance of peel-off.

JAEA Reports

Questionnaire on the measurement condition of distribution coefficient

Takebe, Shinichi; Kimura, Hideo; Matsuzuru, Hideo; Takahashi, Tomoyuki*; Yasuda, Hiroshi*; Uchida, Shigeo*; Mahara, Yasunori*; Saeki, Akiyoshi*; Sasaki, Noriyuki*; Ashikawa, Nobuo*; et al.

JAERI-Review 2001-015, 81 Pages, 2001/05

JAERI-Review-2001-015.pdf:5.94MB

no abstracts in English

Journal Articles

Intercomparison of measurements and questionnaire on the distribution coefficient

Takahashi, Tomoyuki*; Takebe, Shinichi; Kimura, Hideo; Matsuzuru, Hideo; Yasuda, Hiroshi*; Uchida, Shigeo*; Saeki, Akiyoshi*; Mahara, Yasunori*; Sasaki, Noriyuki*; Ashikawa, Nobuo*; et al.

KURRI-KR-44, p.169 - 176, 2000/02

no abstracts in English

JAEA Reports

Study both for migration in heterogeneous permeability/sorption field and for behavior of FP migration in near-field. Vol.II Behavior of FP migration in near-field

Ikeda, Takao*; Amaya, Takayuki*; Chiba, Tamotsu*

PNC TJ1281 97-004, 42 Pages, 1997/03

PNC-TJ1281-97-004.pdf:0.78MB

It is very important to explain the sorption mechanisms of relevant radionuclides, for the performance assessment of geological disposal and for the technical development of engineering barrier system. In the previous studies 1993-1996, these tests were carried out to understand sorption mechanism of SN; -solubility tests -sorption tests onto bentonite, pure montmorillonite, A-FEO(OH) -extraction tests from these minerals -sorption tests onto tuff as a next step, these tests were carried out ragarding SN in this study; -diffusion tests (in-diffusion) -tests for effect of SN concentration and ionic strength on sorption -sorption tests onto granite -tests for effect of coexistent ions on solubility

Journal Articles

Adsorption of Sn(IV) on Goethite in 0.01M NaCl Solution at Ambient Temperature

Amaya, Takayuki*; Suzuki, Kazunori*; Oda, Chie; Yoshikawa, Hideki; Yui, Mikazu

Materials Research Society Symposium Proceedings, p.819 - 826, 1997/00

None

Journal Articles

Solubility of Sn(IV) oxide in dilute NaClO$$_{4}$$ solution at ambient temperature

Amaya, Takayuki*; Suzuki, Kazunori*; Chiba, Tamotsu*; Oda, Chie; Yoshikawa, Hideki; Yui, Mikazu

Materials Research Society Symposium Proceedings, Vol.465, p.751 - 758, 1997/00

None

Oral presentation

Evaluation of fission product release and transport behavior during severe accident focusing on the chemical forms, 4; Development of "in situ" measurement technology for evaluating chemical form of released FP

Iwasaki, Maho; Tanaka, Kosuke; Sato, Isamu; Miwa, Shuhei; Osaka, Masahiko; Amaya, Masaki; Koyama, Shinichi; Seki, Takayuki*; Tokoro, Daishiro*; Ishigamori, Toshio*

no journal, , 

no abstracts in English

Oral presentation

Oxidation behavior of cladding material with SiC coating under LOCA condition

Usui, Takahiro; Sawada, Akihiko; Amaya, Masaki; Suzuki, Akihiro*; Terai, Takayuki*

no journal, , 

Coating on cladding material is one of the candidate as "Accident Toralent Fuel". In this study, SiC coating was fabricated on SUS316 substrate and performed oxdation experiment under LOCA condition. Oxidation of iron decreased in the specimen with coating. The specimen coated for 1 hour showed the best integrity of oxidation.

Oral presentation

SiC coating as hydrogen permeation reduction and oxidation resistance for nuclear fuel cladding

Usui, Takahiro*; Sawada, Akihiko; Amaya, Masaki; Suzuki, Akihiro*; Chikada, Takumi*; Terai, Takayuki*

no journal, , 

SiC coatings were fabricated on SUS316 and Zircaloy-4 substrate. Hydrogen permeation experiment and oxidation experiment were performed. From hydrogen permeation experiment to SiC coated specimen on SUS316 subsrate, permeability of specimen was smaller in one order in magnitude than that of uncoated. From oxidation experiment on Zircaloy-4 substrate, weight gain and thickness of oxide film decreased. Specimens with thicker coating has less weight gain than that with thinner coating, however, thicker coating was peeled off more than thinner coating after oxidized in 1200$$^{circ}$$C.

Oral presentation

Oxidation behavior of SiC coating on nuclear fuel cladding

Usui, Takahiro; Komiyama, Daisuke; Amaya, Masaki; Suzuki, Akihiro*; Terai, Takayuki*

no journal, , 

Oxidation experiments of the SiC coating on the Zry-4 plates were conducted. It was observed that the SiC coating on the Zry-4 specimens has oxidation resistance at 1200$$^{circ}$$C for 30 min. The peel-off of the coating were observed at 1000$$^{circ}$$C and more. It is possible that the peel-off of the coating was affected by the reaction between SiC coating and Zry-4 substrates.

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