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Journal Articles

Investigation of the impact of the prediction accuracy of the burn-up code system SWAT4.0 on neutronics calculation

Tada, Kenichi; Sakino, Takao*

Proceedings of 11th International Conference on Nuclear Criticality Safety (ICNC 2019) (Internet), 9 Pages, 2019/09

Criticality safety of the fuel debris is one of the most important issues, and the adoption of burnup credit is desired. To adopt the burnup credit, validation of the burnup calculation codes is required. In this study, assay data of the used nuclear fuel (2F2DN23, 2F1ZN2, and 2F1ZN3) are evaluated to validate the SWAT4.0 code. The calculation results revealed that the number densities of many heavy nuclides and fission products show good agreement with the experimental data. To investigate the applicability of SWAT4.0 to the criticality safety evaluation of fuel debris, we evaluated the effect of isotopic composition difference on $$k_{eff}$$. The differences in the number densities of U-235, Pu-239, Pu-241, and Sm-149 have a large impact on $$k_{eff}$$. However, the reactivity uncertainty related to the burnup analysis was less than 3%. SWAT4.0 appropriately analyses the isotopic composition of BWR fuel, and it has sufficient accuracy to be adopted in the burnup credit evaluation of fuel debris.

JAEA Reports

Analysis of post irradiation examination of used BWR fuel with SWAT4.0

Kikuchi, Takeo; Tada, Kenichi; Sakino, Takao; Suyama, Kenya

JAEA-Research 2017-021, 56 Pages, 2018/03

JAEA-Research-2017-021.pdf:2.15MB

The criticality management of the fuel debris is one of the most important research issues in Japan. The current criticality management adopts the fresh fuel assumption. The adoption of the fresh fuel assumption for the criticality control of the fuel debris is difficult because the k$$_{rm eff}$$ of the fuel debris could exceed 1.0 in most of cases which the fuel debris contains water and does not contain neutron absorbers such as gadolinium. Therefore, the adoption of the burnup credit is considered. The prediction accuracy of the isotopic composition of used nuclear fuel must be required to adopt the burnup credit for the treatment of the fuel debris. JAEA developed a burnup calculation code SWAT4.0 to obtain reference calculation results of the isotopic composition of the used nuclear fuel. This code is used to evaluate the composition of fuel debris. In order to investigate the prediction accuracy of SWAT4.0, we analyzed the PIE of BWR obtained from 2F2DN23.

Journal Articles

Analysis of used BWR fuel assay data with the integrated burnup code system SWAT4.0

Tada, Kenichi; Kikuchi, Takeo*; Sakino, Takao; Suyama, Kenya

Journal of Nuclear Science and Technology, 55(2), p.138 - 150, 2018/02

 Times Cited Count:2 Percentile:33.17(Nuclear Science & Technology)

The criticality safety of the fuel debris in Fukushima Daiichi Nuclear Power Plant is one of the most important issues and the adoption of the burnup credit is desired for the criticality analysis. The assay data of used nuclear fuel irradiated in 2F2 is evaluated to validate SWAT4.0 for BWR fuel burnup problem. The calculation results revealed that number density of many heavy nuclides and FPs showed good agreement with the experimental data except for $$^{235}$$U, $$^{237}$$Np, $$^{238}$$Pu and Sm isotopes. The cause of the difference is assumption of the initial number density and void ratio and overestimation of the capture cross section of $$^{237}$$Np. The C/E-1 values do not depend on the types of fuel rods (UO$$_{2}$$ or UO$$_{2}$$-Gd$$_{2}$$O$$_{3}$$) and it is similar to that for the PWR fuel. These results indicate that SWAT4.0 appropriately analyzes the isotopic composition of the BWR fuel and it has sufficient accuracy to be adopted in the burnup credit evaluation of the fuel debris.

Journal Articles

Additional function of JAERI Material Performance Database (JMPD)

Kaji, Yoshiyuki; Sakino, Takao*; Tsuji, Hirokazu

Proceedings of 10th German-Japanese Workshop on Chemical Information, p.67 - 70, 2002/00

The JAERI Material Performance Database (JMPD) was developed with a view to utilizing material performance data efficiently. Data from more than 11,500 test pieces are prepared for data evaluation in the JMPD. Some kinds of data analyses have been performed by utilizing the JMPD. As for improvement of user interfaces, graphic function and modification function of the data were added in the JMPD. The following important points will be emphasized in the future direction of the JMPD; (1) enrichment of the stored data in both of the core and the surrounding portions of the JMPD, (2) improvement of user-friendliness, (3) construction and enrichment of data networking system, and (4) construction of knowledge base.

Journal Articles

Development and utilization of material database of JAERI

Kaji, Yoshiyuki; Sakino, Takao*; Ugachi, Hirokazu; Tsuji, Hirokazu

"Fukanteki Kanten Karano Kogaku" Shimpojiumu Shiryoshu, p.175 - 178, 2000/11

no abstracts in English

Journal Articles

Present status and future direction of JAERI material performance database (JMPD)

Kaji, Yoshiyuki; Sakino, Takao*; Ugachi, Hirokazu; Tsuji, Hirokazu

Proceedings of 9th German-Japanese Workshop on Chemical Information, p.121 - 124, 2000/00

no abstracts in English

Journal Articles

Data-Free-Way; Attempt at developing distributed database for nuclear materials

Kinugawa, Junichi*; Fujita, Mitsutane*; Noda, Tetsuji*; Tsuji, Hirokazu; Kaji, Yoshiyuki; Sakino, Takao*; Tachi, Yoshiaki*; Kaneda, Kenichiro*; Mashiko, Shinichi*; Shimura, Kazuki*; et al.

Proceedings of 9th German-Japanese Workshop on Chemical Information, p.134 - 135, 2000/00

no abstracts in English

JAEA Reports

Retrieval results on various properties of superalloy using ``data-free-way'' (Joint research)

Kaji, Yoshiyuki; Tsuji, Hirokazu; Sakino, Takao*; Fujita, Mitsutane*; Kinugawa, Junichi*; Tachi, Yoshiaki*; Saito, Junichi*; Kano, Shigeki*; Shimura, Kazuki*; Nakajima, Ritsuko*; et al.

JAERI-Tech 99-007, 32 Pages, 1999/02

JAERI-Tech-99-007.pdf:1.53MB

no abstracts in English

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