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Journal Articles

Development of phenomenological degradation models for Cr-Coated Zr alloy cladding under high-temperature oxidation conditions

Taniguchi, Yoshinori; Luu, V. N.; Tasaki, Yudai; Udagawa, Yutaka; Katsuyama, Jinya

Annals of Nuclear Energy, 231, p.112177_1 - 112177_16, 2026/06

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

Journal Articles

Analysis of fracture conditions of Cr-coated Zr alloy claddings under LOCA conditions calculated using FEMAXI fuel performance code

Luu, V. N.; Taniguchi, Yoshinori; Udagawa, Yutaka; Tasaki, Yudai; Katsuyama, Jinya

Annals of Nuclear Energy, 230, p.112114_1 - 112114_14, 2026/06

 Times Cited Count:1 Percentile:98.37(Nuclear Science & Technology)

Journal Articles

High-temperature oxidation failure in reactivity-initiated accidents; An Evaluation of failure criteria based on oxygen concentration from the previous NSRR experiments

Luu, V. N.; Taniguchi, Yoshinori; Udagawa, Yutaka; Katsuyama, Jinya

Nuclear Engineering and Design, 442, p.114222_1 - 114222_15, 2025/10

 Times Cited Count:2 Percentile:83.88(Nuclear Science & Technology)

Journal Articles

Updating fission product chemistry database based on recent investigation in Fukushima-Daiichi Nuclear Power Station, 3; High-temperature thermochemistry of CaCO$$_{3}$$-CsOH

Rizaal, M.; Luu, V. N.; Nakajima, Kunihisa; Miwa, Shuhei

Proceedings of International Topical Workshop on Fukushima Decommissioning Research 2024 (FDR2024) (Internet), 4 Pages, 2024/10

Journal Articles

Updating fission product chemistry database based on recent investigation in Fukushima-Daiichi Nuclear Power Station, 2; Temperature effects on the deposition behavior of CsOH aerosols on concrete main phase-CaCO$$_{3}$$

Luu, V. N.; Nakajima, Kunihisa; Rizaal, M.; Miwa, Shuhei

Proceedings of International Topical Workshop on Fukushima Decommissioning Research 2024 (FDR2024) (Internet), 4 Pages, 2024/10

Journal Articles

Experimental determination of deposition velocity of CsOH aerosols on CaCO$$_{3}$$ at temperature range 170 - 290$$^{circ}$$C

Luu, V. N.; Nakajima, Kunihisa

Nuclear Engineering and Design, 426, p.113402_1 - 113402_7, 2024/09

 Times Cited Count:2 Percentile:47.49(Nuclear Science & Technology)

Journal Articles

Characterization of Cs deposits formed by the interaction of simulated fission product CsOH in the gas phase and concrete at 200$$^{circ}$$C

Luu, V. N.; Nakajima, Kunihisa

Mechanical Engineering Journal (Internet), 11(2), p.23-00446_1 - 23-00446_11, 2024/01

Journal Articles

Surface analyses of CsOH chemisorbed on concrete and aggregate at around 200$$^{circ}$$C

Luu, V. N.; Nakajima, Kunihisa

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 9 Pages, 2023/05

Journal Articles

Study on cesium compound formation by chemical interaction of CsOH and concrete at elevated temperatures

Luu, V. N.; Nakajima, Kunihisa

Journal of Nuclear Science and Technology, 60(2), p.153 - 164, 2023/02

 Times Cited Count:7 Percentile:63.77(Nuclear Science & Technology)

Oral presentation

Updating fission product chemistry database based on recent investigation in Fukushima-Daiichi Nuclear Power Station, 1; Overview of fundamental study related to fission product chemistry

Miwa, Shuhei; Nakajima, Kunihisa; Karasawa, Hidetoshi; Rizaal, M.; Luu, V. N.; Mohamad, A. B.

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Oral presentation

Oral presentation

Oral presentation

Study on FP chemistry for improvement of LWR source term

Rizaal, M.; Nakajima, Kunihisa; Karasawa, Hidetoshi; Luu, V. N.; Miwa, Shuhei

no journal, , 

Oral presentation

Evaluation of Cs deposition mechanism between shield plugs, 1; Estimation of Cs deposition by FP behavior models using for severe accident analysis

Karasawa, Hidetoshi; Rizaal, M.; Luu, V. N.; Nakajima, Kunihisa; Miwa, Shuhei; Kino, Chiaki*

no journal, , 

We are investigating the Cs accumulation mechanism between shield plugs observed in the Fukushima Daiichi Nuclear Power Plant accident. Previously, it was thought that there was no gas flow path in the gap between the shield plugs, but it was found that a high concentration of Cs-137 was accumulated. Also, the Nuclear Regulatory Commission clarified that the deformation of the shield plug due to gravity causes the formation of a gas flow path. In this study, the chemical adsorption rate of CsOH aerosol on concrete was added to the FP transfer behavior analysis module of the severe accident analysis code SAMPSON, and a trial analysis was performed on the shield plug of Unit 2. Then, the effects of gap spacing between shield plugs, gas flow velocity, gas temperature, CsOH aerosol concentration, etc. on Cs accumulation are evaluated, and the main mechanisms of Cs accumulation are examined.

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