Refine your search:     
Report No.
 - 
Search Results: Records 1-5 displayed on this page of 5
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Coupled computer code study on irradiation performance of a fast reactor mixed oxide fuel element with an emphasis on the fission product cesium behavior

Uwaba, Tomoyuki; Nemoto, Junichi*; Ishitani, Ikuo*; Ito, Masahiro*

Nuclear Engineering and Design, 331, p.186 - 193, 2018/05

 Times Cited Count:4 Percentile:38.58(Nuclear Science & Technology)

A computer code for the analysis of the overall irradiation performance of a fast reactor mixed-oxide (MOX) fuel element was coupled with a specialized code for the analysis of fission product cesium behaviors in a MOX fuel element. The coupled code system allowed for the analysis of the radial and axial Cs migrations, the generation of Cs chemical compounds and fuel swelling due to Cs-fuel-reactions in association with the thermal and mechanical behaviors of the fuel element. The coupled code analysis was applied to the irradiation performance of a fast reactor MOX fuel element attaining high burnup for discussion on the axial distribution of Cs, fuel-to-cladding mechanical interaction owing to the Cs-fuel-reactions by comparing the calculated results with post irradiation examinations.

Journal Articles

Behavior of cesium molybdate, Cs$$_{2}$$MoO$$_{4}$$, in severe accident conditions, 1; Partitioning of Cs and Mo among gaseous species

Do, Thi Mai Dung*; Sujatanond, S.*; Ogawa, Toru

Journal of Nuclear Science and Technology, 55(3), p.348 - 355, 2018/03

 Times Cited Count:6 Percentile:52.79(Nuclear Science & Technology)

In order to better understand the behavior of cesium in the severe accident of the LWR, the high-temperature chemistry of Cs$$_{2}$$MoO$$_{4}$$ in H$$_{2}$$O+H$$_{2}$$ gas was studied. The pseudo-binary system, Cs$$_{2}$$MoO$$_{4}$$-MoO$$_{3}$$, was thermochemically modeled with Redlich-Kister formulation to form a basis to analyze the high-temperature behavior of Cs$$_{2}$$MoO$$_{4}$$. The model prediction was compared with the thermogravimetric measurements of Cs$$_{2}$$MoO$$_{4}$$ in dry and humid argon, which revealed that the mass-loss rate was enhanced in the humid atmosphere. Thermochemical model was further applied to predict the partitioning of cesium and molybdenum among gaseous species in the BWR core degradation condition typical of Short-Term Station Blackout.

Journal Articles

Thermal expansion and thermal conductivity of cesium molybdate

Minato, Kazuo; Takano, Masahide; Fukuda, Kosaku; Sato, Seichi*; Ohashi, Hiroshi*

Journal of Alloys and Compounds, 255, p.18 - 23, 1997/00

 Times Cited Count:14 Percentile:66.91(Chemistry, Physical)

no abstracts in English

Journal Articles

Thermal properties of cesium molybdate

Minato, Kazuo; Takano, Masahide*; Sato, Seichi*; Ohashi, Hiroshi*; Fukuda, Kosaku

Transactions of the American Nuclear Society, 74, p.95 - 96, 1996/00

no abstracts in English

Oral presentation

Experimental studies on Cs chemisorption on reactor structural materials and their behaviour at high temperature

Suzuki, Eriko; Di Lemma, F. G.; Nakajima, Kunihisa; Yamashita, Shinichiro; Osaka, Masahiko

no journal, , 

In order to clarify the re-vaporization behavior of cesium (Cs) chemisorbed compounds which formed onto reactor structural materials during Severe Accident (SA), Cs chemisorbed samples were reheated at 1000$$^{circ}$$C and then microstructural analysis of the chemisorbed samples was conducted. In the case of stainless steel containing Mo, Cs-Mo-O compounds were formed on surface, together with major Cs-Fe-Si-O compounds, and re-vaporized easier than Cs-Fe-Si-O compounds at 1000$$^{circ}$$C.

5 (Records 1-5 displayed on this page)
  • 1