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Journal Articles

Chemisorption behavior of CsOH vapor on UO$$_{2}$$ under high temperatures and various water vapor concentrations

Mohamad, A. B.; Nakajima, Kunihisa; Imoto, Jumpei*; Takano, Masahide

Journal of Nuclear Materials, 631, p.156826_1 - 156826_12, 2026/09

 Times Cited Count:0 Percentile:0.00(Materials Science, Multidisciplinary)

Journal Articles

Microstructural evolution and mechanical hardening of Cr-coated MDA cladding under high-dose Fe ion irradiation

Mohamad, A. B.; Chen, J.*; Ioka, Ikuo*; Suzuki, Eriko; Kondo, Keietsu; Abe, Yosuke; Yamashita, Shinichiro; Okubo, Nariaki; Nemoto, Yoshiyuki; Okada, Yuji*; et al.

Journal of Nuclear Materials, 625, p.156513_1 - 156513_9, 2026/04

 Times Cited Count:0 Percentile:0.00(Materials Science, Multidisciplinary)

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

Estimation of the oxidation and hydrogen absorption behavior during simulated accidental condition of Zircaloy-4 with Cr coating formed by electrochemical plating

Kawai, Keito*; Nemoto, Yoshiyuki; Fujimura, Yuki; Kondo, Keietsu; Abe, Yosuke; Mohamad, A. B.; Pham, V. H.; Ishikawa, Norito; Ishijima, Yasuhiro; Ioka, Ikuo; et al.

Nihon Genshiryoku Gakkai Wabun Rombunshi (Internet), 24(3), p.82 - 98, 2025/08

An accident tolerant fuel (ATF) cladding, which is more resistant to accidents than the conventional Zircaloy cladding, is under development. One of these claddings is a chromium (Cr)-coated cladding with an outer surface coated with Cr, which is expected to improve the resistance to high-temperature steam oxidation. In this study, electrochemical plating was applied to coat a Cr layer on the cladding outer surface, and its properties under accidental conditions were evaluated. In a loss-of-coolant accident (LOCA), the cladding will burst and both the outer and inner surfaces of the cladding will be oxidized. Thus, as-received Zircaloy-4 and Cr-coated claddings were tested for oxidation in high-temperature steam to investigate differences in oxidation behavior, hydrogen absorption behavior, and mechanical properties after oxidation. Oxidation tests were conducted using a thermobalance. The amount of oxidation of coated samples decreased by half compared with that of uncoated samples, indicating that the coating was effective in inhibiting oxidation. However, the hydrogen absorption of coated samples was found to be higher than that of uncoated samples. In this paper, we discuss the mechanism behind this difference in hydrogen absorption and its effect on mechanical properties.

Journal Articles

None

Hirooka, Shun; Horii, Yuta; Hayashizaki, Kohei; Mohamad, A. B.

Kaku Nenryo, (60-1), p.17 - 20, 2025/02

no abstracts in English

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

Modeling of the P2M past fuel melting experiments with the FEMAXI-8 code

Mohamad, A. B.; Udagawa, Yutaka

Nuclear Technology, 210(2), p.245 - 260, 2024/02

 Times Cited Count:2 Percentile:25.59(Nuclear Science & Technology)

Journal Articles

Microstructural evolution of intermetallic phase precipitates in Cr-coated zirconium alloy cladding in high-temperature steam oxidation up to 1400$$^{circ}$$C

Mohamad, A. B.; Nemoto, Yoshiyuki; Furumoto, Kenichiro*; Okada, Yuji*; Sato, Daiki*

Corrosion Science, 224, p.111540_1 - 111540_15, 2023/11

 Times Cited Count:13 Percentile:62.91(Materials Science, Multidisciplinary)

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:9.19(Nuclear Science & Technology)

Oral presentation

High-throughput experiments on Cr-rich particle formation in Fe-Cr-Al alloys using combinatorial samples with continuous concentration gradients

Abe, Yosuke; Mohamad, A. B.; Sasaki, Taisuke*; Yamashita, Shinichiro; Okubo, Nariaki; Ukai, Shigeharu

no journal, , 

Embrittlement due to the formation of Cr-rich embrittlement phases ($$alphaprime$$ particles) is a concern in Fe-Cr-Al (ODS) alloys being developed as accident tolerant fuel cladding for light water reactors, but the compositional range of Cr and Al in which embrittlement occurs has not been determined. In this study, combinatorial samples with continuous concentration gradients were prepared by interdiffusion heat treatment of Fe-Cr-Al alloys, and high-throughput composition and hardness measurements were performed before and after thermal aging. The compositional range obtained was sufficient to determine the precipitation boundaries of the $$alphaprime$$ particles. Solid solution strengthening was studied from the hardness data after diffusion heat treatment, suggesting that slow cooling leads to spinodal decomposition and formation of Al precipitates. The precipitation boundary of $$alphaprime$$ particles was refined from the hardness data after thermal aging.

Oral presentation

Oxidation and hydrogen absorption behavior of Cr coated Zry4 in high temperature steam

Kawai, Keito*; Nemoto, Yoshiyuki; Fujimura, Yuki; Kondo, Keietsu; Abe, Yosuke; Mohamad, A. B.; Pham, V. H.; Ishikawa, Norito; Ishijima, Yasuhiro; Ioka, Ikuo; et al.

no journal, , 

no abstracts in English

Oral presentation

None

Ioka, Ikuo*; Mohamad, A. B.; Nemoto, Yoshiyuki; Yamashita, Shinichiro; Sato, Daiki*; Okada, Yuji*

no journal, , 

no abstracts in English

Oral presentation

The Behavior of Cr-coated Zry cladding under high-temperature steam oxidation

Mohamad, A. B.; Furumoto, Kenichiro; Nemoto, Yoshiyuki; Ioka, Ikuo; Sato, Daiki*; Okada, Yuji*; Yamashita, Shinichiro; Osaka, Masahiko

no journal, , 

Oral presentation

Study on coating technic to enhance accident tolerance of fuel cladding, 1; Overview of accident tolerant coating technic studies and apparatus development in JAEA

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

no journal, , 

JAEA is conducting research on various coating technologies for fuel cladding tubes aimed at improving accident resistance. In the lecture, we will introduce new equipment development at JAEA aimed at using these studies in addition to an overview of the entire project.

Oral presentation

Study on coating technic to enhance accident tolerance of fuel cladding, 2-1; Overview of accident tolerant coating technic studies and apparatus development in JAEA

Mohamad, A. B.; Nemoto, Yoshiyuki; Soma, Yasutaka; Ishijima, Yasuhiro; Sato, Tomonori; Ioka, Ikuo; Pham, V. H.; Miwa, Shuhei; Nakajima, Kunihisa; Kaji, Yoshiyuki; et al.

no journal, , 

JAEA is promoting the characterization of various coating tubes as part of fundamental research that contributes to the practical application of coated fuel cladding aiming at improving accident tolerance. In this presentation, overall outline, the new test equipment under construction, and highlight results of the vapor oxidation characteristic evaluation test for coated claddings will be presented.

Oral presentation

The Behavior of Cr-coated Zry cladding above the eutectic temperature

Mohamad, A. B.; Nemoto, Yoshiyuki; Furumoto, Kenichiro*; Okada, Yuji*; Sato, Daiki*

no journal, , 

Oral presentation

Technical basis development for the introduction of ATF cladding materials into existing light water reactors

Mohamad, A. B.; Chen, J.*; Ioka, Ikuo; Yamashita, Shinichiro

no journal, , 

no abstracts in English

Oral presentation

Status of development and overview of R&D in Japan

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

no journal, , 

Oral presentation

R&D and implementation effort at JAEA on ATF

Miwa, Shuhei; Yamashita, Shinichiro; Nemoto, Yoshiyuki; Okubo, Nariaki; Abe, Yosuke; Soma, Yasutaka; Mohamad, A. B.; Katsuyama, Jinya; Udagawa, Yutaka; Kaji, Yoshiyuki

no journal, , 

Oral presentation

High-throughput nanoindentation mapping of Alpha-Prime precipitates in ion-irradiated combinatorial FeCrAl alloys

Ukai, Shigeharu; Abe, Yosuke; Geng, D.*; Kubo, Atsushi; Sasaki, Taisuke*; Mohamad, A. B.; Fujita, Yohei*; Okubo, Nariaki; Yamashita, Shinichiro; Yu, H.*; et al.

no journal, , 

A combinatorial specimen with a continuous compositional gradient of Cr and Al in FeCrAl alloys was fabricated, and by integrating an ion irradiation with continuous stiffness nanoindentation measurement, high-throughput dataset was created. It was clarified for the first time, that alpha-prime precipitation occurs within subtle two-dimensional (Cr, Al) composition; about 5 at.% Al addition accelerates alpha-prime formation, and spinodal decomposition becomes dominant at more than 30 at.% Cr. It was also clarified that alpha-prime precipitation reaches saturation at an irradiation dose as low as 1.44 dpa (0.64 dpa).

38 (Records 1-20 displayed on this page)