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Journal Articles

Development of an integrated computer code system for analyzing irradiation behaviors of a fast reactor fuel

Uwaba, Tomoyuki; Nemoto, Junichi*; Ito, Masahiro*; Ishitani, Ikuo*; Doda, Norihiro; Tanaka, Masaaki; Otsuka, Satoshi

Nuclear Technology, 207(8), p.1280 - 1289, 2021/08

 Times Cited Count:3 Percentile:34.82(Nuclear Science & Technology)

Computer codes for irradiation behavior analysis of a fuel pin and a fuel pin bundle and for coolant thermal hydraulics analysis were coupled into an integrated code system. In the system, each code provides data required by other codes and the analyzed results are shared among them. The system allows for the synthesizing of analyses of thermal, chemical and mechanical behaviors in a fuel subassembly under irradiation. A test analysis was made for a fuel subassembly containing a mixed oxide fuel pin bundle irradiated in a fast reactor. The results of the analysis were presented with transverse cross-sectional images of the fuel subassembly and three-dimensional images of a fuel pin and fuel pin bundle models. For detailed evaluation, various irradiation behaviors of all fuel pins in the subassembly were analyzed and correlated with irradiation conditions.

Journal Articles

Engineering aspects in modeling of high burnup LWR fuel behavior

Suzuki, Motoe

Proceedings of 2nd Japan-Korea-China (5th Japan-Korea) Seminar on Nuclear Reactor Fuel and Materials, p.4 - 10, 2004/03

In designing a fuel performance code which describes complicated interactions working in high burnup fuel, the code will inevitably become a complex structure of inter-dependent models. In normal operation conditions, PCMI occurs and the pellet-clad firm bonding layer makes the cladding to be subjected to a bi-axial stress state, i.e. under tough mechanical loading. In contrast, the bonding layer enhances thermal conductance, decreases the pellet temperature and keeps the pellet-clad contact, resulting in increased resistance against the Lift-Off. For pellet behaviors, the fission gas bubble growth is strongly dependent on temperature, so that a reliable prediction of fuel temperature is required by pellet radial meshing which can fully accommodate the burning analysis results and the rim structure growth. The presentation deals with modeling method in terms of specific aspects such as meshing.

JAEA Reports

Verification of computer code FPRETAIN with respect to RIA data from SPERT and PBF experiments

Y.-H.Heo*; Yanagisawa, Kazuaki

JAERI-M 92-195, 19 Pages, 1992/12

JAERI-M-92-195.pdf:0.47MB

no abstracts in English

JAEA Reports

Oral presentation

Fuel safety research at JAEA

Amaya, Masaki

no journal, , 

no abstracts in English

Oral presentation

Overview of research activities of the Fuel Safety Research Group

Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori; Kakiuchi, Kazuo; Tasaki, Yudai; Udagawa, Yutaka

no journal, , 

no abstracts in English

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