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Journal Articles

On-going R&D program at JAEA on the Advanced Technology Fuels; An Update on the Cr-coated Zry cladding research

Mohamad, A. B.; Yamashita, Shinichiro; Nemoto, Yoshiyuki; Abe, Yosuke; Pham, V. H.; Ioka, Ikuo; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Rizaal, M.; et al.

Proceedings of TopFuel 2025; Nuclear Reactor Fuel Performance Conference (Internet), 8 Pages, 2025/10

Journal Articles

Impact of molybdenum on iodine chemistry during fission product transport phenomenology

Rizaal, M.; Nakajima, Kunihisa; Suzuki, Eriko; Miwa, Shuhei

Annals of Nuclear Energy, 218, p.111433_1 - 111433_10, 2025/08

 Times Cited Count:1 Percentile:59.09(Nuclear Science & Technology)

Journal Articles

Chemical interaction of CsOH vapor with UO$$_{2}$$ and Fe-Zr melt

Nakajima, Kunihisa; Takano, Masahide

Journal of Nuclear Science and Technology, 62(1), p.78 - 85, 2025/01

 Times Cited Count:3 Percentile:60.19(Nuclear Science & Technology)

At TEPCO's Fukushima Daiichi Nuclear Power Station, it is estimated that considerable amounts of cesium still remain in the reactors from the analysis results using the severe accident analysis codes and the reverse analysis from contaminated water. Since cesium is known to form stable compounds with uranium and zirconium, chemisorption experiments with uranium dioxide pellets and iron-zirconium melts for cesium hydroxide vapor were carried out. As the results, formations of cesium uranate, Cs$$_{2}$$UO$$_{4}$$, and cesium zirconate, Cs$$_{2}$$ZrO$$_{3}$$, were confirmed, indicating that cesium was chemisorbed on both of the uranium dioxide pellets and the iron-zirconium melts in an Ar-H$$_{2}$$-H$$_{2}$$O flow and an Ar-H$$_{2}$$ flow, respectively. Therefore, it was considered that cesium released from fuel might be trapped by chemisorption with fuels and/or iron-zirconium melts during light water reactor severe accidents.

Journal Articles

Water-leaching behavior for cesium chemisorbed on stainless steel at room temperature

Nakajima, Kunihisa; Imoto, Jumpei*; Nishioka, Shunichiro*; Osaka, Masahiko; Miwa, Shuhei

Journal of Nuclear Science and Technology, 62, 10 Pages, 2025/00

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

Water-leaching tests at 303 K were performed on cesium (Cs) chemisorbed on stainless steels to investigate its long-term dissolution behavior. The findings showed that Cs continued to dissolve into water even after 1200 hours and that Cs was found to coexist with silicon as ring-shaped particles. This indicates that even water-insoluble Cs, which is defined in the Cs-chemisorption models incorporated into existing SA analysis codes, can dissolve in water over extended periods, with the dissolution attributed to the ring-shaped Cs silicate particles. Additionally, these water-leaching behaviors were accurately described by the Noyes-Whitney equation, suggesting the potential development of a water-dissolution model for the water-insoluble Cs in the chemisorption models. These insights imply that long-term redistributions of chemisorbed Cs could occur within the reactor pressure vessels in Fukushima Daiichi Nuclear Power Station, necessitating a water-dissolution model to predict redistributions through the aqueous phase.

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

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

On-going R&D program at JAEA on the accident tolerant fuels

Mohamad, A. B.; Soma, Yasutaka; Nemoto, Yoshiyuki; Abe, Yosuke; Ioka, Ikuo; Sato, Tomonori; Ishijima, Yasuhiro; Miwa, Shuhei; Nakajima, Kunihisa; Yamashita, Shinichiro; et al.

Proceedings of TopFuel 2024 (Internet), 8 Pages, 2024/10

Journal Articles

Advances in understanding cesium retention on calcium silicate material

Rizaal, M.; Nakajima, Kunihisa

Chemosphere, 363, p.142870_1 - 142870_9, 2024/09

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:44.79(Nuclear Science & Technology)

Journal Articles

Gaseous and aerosol formations in the pseudo-binary CsI-MoO$$_{3}$$ reaction system

Rizaal, M.; Nakajima, Kunihisa; Suzuki, Eriko; Miwa, Shuhei

Proceedings of 11th European Review Meeting on Severe Accident Research Conference (ERMSAR 2024) (Internet), 11 Pages, 2024/05

Journal Articles

Cohesive/Adhesive strengths of CsOH-chemisorbed SS304 surfaces

Li, N.*; Sun, Y.*; Nakajima, Kunihisa; Kurosaki, Ken*

Journal of Nuclear Science and Technology, 61(3), p.343 - 353, 2024/03

 Times Cited Count:1 Percentile:13.88(Nuclear Science & Technology)

During the Fukushima Daiichi nuclear power plant (1F) accident, an overwhelming amount of the cesium remaining in the pressure vessel could have been deposited onto 304 stainless steel (SS304) steam separators and dryers, both with large surface areas. During 1F's decommissioning, the deposited cesium is a safety hazard as it can generate radioactive dust. However, the cohesive and adhesive strengths of CsOH-chemisorbed oxide scales are yet to be defined. In this study, we investigated how CsOH-chemisorption affects the cohesive and adhesive strengths between oxide scales and SS304 substrates with a scratch tester. The scratch test results revealed that the cohesive strengths of the oxide scales decreased after CsOH-chemisorption, while adhesive failure could not be reached.

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

Chemical interaction between Sr vapor species and nuclear reactor core structure

Mohamad, A. B.; Nakajima, Kunihisa; Miwa, Shuhei; Osaka, Masahiko

Journal of Nuclear Science and Technology, 60(3), p.215 - 222, 2023/03

 Times Cited Count:1 Percentile:10.16(Nuclear Science & Technology)

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:62.74(Nuclear Science & Technology)

JAEA Reports

Improvement of model for cesium chemisorption onto stainless steel in severe accident analysis code SAMPSON (Joint research)

Miwa, Shuhei; Karasawa, Hidetoshi; Nakajima, Kunihisa; Kino, Chiaki*; Suzuki, Eriko; Imoto, Jumpei

JAEA-Data/Code 2021-022, 32 Pages, 2023/01

JAEA-Data-Code-2021-022.pdf:1.41MB
JAEA-Data-Code-2021-022(errata).pdf:0.17MB

The improved model for cesium (Cs) chemisorption onto stainless steel (SS) in the fission product (FP) chemistry database named ECUME was incorporated into the severe accident (SA) analysis code SAMPSON for the more accurate estimation of Cs distribution within nuclear reactor vessels in the TEPCO's Fukushima Daiichi Nuclear Power Station (1F). The SAMPSON with the improved model was verified based on the analysis results reproducing the experimental results which were subjected to the modeling of Cs chemisorption behavior. Then, the experiment in the facility with the temperature gradient tube to simulate SA conditions such as temperature decrease and aerosol formation was analyzed to confirm availability of the improved model to the analysis of Cs chemisorption onto SS. The SAMPSON with the improved model successfully reproduced the experimental results, which indicates that the improved model and the analytical method such as setting a method of node-junction, models of aerosol formation and the calculation method of saturated CsOH vapor pressure can be applicable to the analysis of Cs chemisorption behavior. As the information on water-solubility of Cs deposits was also prerequisite to estimate the Cs distribution in the 1F because Cs can be transported through aqueous phase after the SA, the water-solubility of chemisorbed Cs compounds was investigated. The chemisorbed compounds on SS304 have been identified to CsFeO$$_{2}$$ at 873 K to 973 K with higher water-solubility, CsFeSiO$$_{4}$$ at 973 K to 1273 K and Cs$$_{2}$$Si$$_{4}$$O$$_{9}$$ at 1073 K to 1273 K with lower water-solubility. From these results, the water-solubility of chemisorbed Cs compounds can be estimated according to the SA analysis conditions such as temperature in the reactor and the CsOH concentration affecting the amount of chemisorbed Cs.

Journal Articles

High-temperature gaseous reaction of cesium with siliceous thermal insulation; The Potential implication to the provenance of enigmatic Fukushima cesium-bearing material

Rizaal, M.; Nakajima, Kunihisa; Saito, Takumi*; Osaka, Masahiko; Okamoto, Koji*

ACS Omega (Internet), 7(33), p.29326 - 29336, 2022/08

 Times Cited Count:6 Percentile:31.65(Chemistry, Multidisciplinary)

Journal Articles

A New method of measuring ruthenium activity in ruthenium-containing alloys by using thermogravimetric analysis

Liu, J.; Nakajima, Kunihisa; Miwa, Shuhei; Shirasu, Noriko; Osaka, Masahiko

Journal of Nuclear Science and Technology, 59(4), p.484 - 490, 2022/04

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

Journal Articles

Cesium chemistry in the LWR severe accident and towards the decommissioning of Fukushima Daiichi Nuclear Power Station

Osaka, Masahiko; Gou$"e$llo, M.*; Nakajima, Kunihisa

Journal of Nuclear Science and Technology, 59(3), p.292 - 305, 2022/03

 Times Cited Count:12 Percentile:74.04(Nuclear Science & Technology)

Research on the fission product chemistry made after the severe accident of the Fukushima Daiichi Nuclear Power Station were reviewed with focus on the Cesium chemistry in terms of two regimes, namely the accidental source term and the long-term source term via aqueous phase towards the decommissioning. For the accidental source term, Cs chemical interaction with Mo, B and Si were reviewed. Regarding the unique issue of long-term source term via aqueous phase, Cs penetration into concrete and fuel debris leaching were mentioned as the main sources of FPs. Efforts on the preparation of thermodynamic data for the Cs complex oxides were described. All these Cs chemical behaviors should be modelled and validated/verified through the analysis and evaluation of the actual samples including fuel debris that would be taken from the Fukushima Daiichi Nuclear Power Station in near future.

Journal Articles

Phase stability of Cs-Si-O and Cs-Si-Fe-O compounds on stainless steel

Suzuki, Chikashi; Nakajima, Kunihisa; Osaka, Masahiko

Journal of Nuclear Science and Technology, 59(3), p.345 - 356, 2022/03

 Times Cited Count:4 Percentile:33.50(Nuclear Science & Technology)

During a severe accident (SA) such as the Fukushima Daiichi Nuclear Power Plant accident, fission products (FP) can be retained on the surface of structural materials in reactors. Cesium (Cs) is an important FP, and various Cs compounds such as Cs silicates are formed on the surface of stainless steel (SS) in a reactor during a SA. We calculated total energies of Cs-Si-O compounds for evaluation on phase stability within an adiabatic approximation. The calculations indicate that Cs$$_{6}$$Si$$_{10}$$O$$_{23}$$ is the most stable of the Cs-Si-O compounds. We calculated, furthermore, total energies of Cs-Si-Fe-O compounds. These calculations indicate that Cs-Si-Fe-O compounds are more stable than C-Si-O compounds and that CsSi$$_{2}$$FeO$$_{6}$$ is the most stable of these C-Si-O and Cs-Si-Fe-O compounds within an adiabatic approximation. The results of our present calculations and our previous experiments lead to the conclusion that Cs-Si-Fe-O compounds can be stably formed on SS surface by Cs chemisorption.

261 (Records 1-20 displayed on this page)