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Collaborative Laboratories for Advanced Decommissioning Science; Japan Agency for Marine-Earth Science and Technology*
JAEA-Review 2026-013, 86 Pages, 2026/07
JAEA-Review-2026-013.pdf:5.3MB
The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), has been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") from FY2019. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station (1F), Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2024, this report summarizes the research results of the "Data-driven on-site diagnostic technology: predicting microbiologically influenced corrosion risk for ensuring long-term integrity" conducted in FY2024. The present study aims to establish an innovative on-site diagnostic protocol capable of predicting microbiologically influenced corrosion (MIC) risks with high accuracy. To achieve this, we combined high-throughput analytical methods, simulated field experiments, and data-driven statistical analyses. Environmental samples were collected in Fukushima Prefecture to characterize microbial community structures and to develop key technologies for on-site genetic diagnostics. Using these samples, we evaluated the iron-corroding potential under various culture conditions and designed experimental systems simulating 1F environment. A high-throughput testing framework was validated for its ability to measure actual iron corrosion. In parallel, statistical approaches integrating microbial community profiles with MIC activity data were applied, yielding useful insights into both their applicability and limitations. Further, fixation methods for microbial observation in corrosion samples were examined, and optimal conditions were identified. Overall, the project provided valuable information on environmental microbial communities, cultivation of corrosion-associated microorganisms, and data-driven statistical approaches. These results lay the groundwork for the development of biomarker-based, ubiquitous diagnostic technologies for MIC applicable to diverse field environments, including those around 1F site.
removal from aqueous solutions; Cost-effectiveness & parametric effectsMaamoun, I.; Eljamal, R.*; Eljamal, O.*
Chemosphere, 312, Part 1, p.137176_1 - 137176_11, 2023/01
Times Cited Count：39 Percentile：88.91(Environmental Sciences)Saito, Kimiaki; Takahara, Shogo; Uezu, Yasuhiro
Nihon Genshiryoku Gakkai-Shi ATOMO
, 60(2), p.111 - 115, 2018/02
no abstracts in English
Chimi, Yasuhiro; Takamizawa, Hisashi; Kasahara, Shigeki*; Iwata, Keiko; Nishiyama, Yutaka
Nuclear Engineering and Design, 307, p.411 - 417, 2016/10
Times Cited Count：1 Percentile：8.80(Nuclear Science & Technology)To investigate influential parameters for irradiation-assisted stress corrosion cracking (IASCC) growth behavior, we attempt to analyze statistically existing data on the crack growth rate (CGR) in irradiated austenitic stainless steels (SSs) in boiling water reactor (BWR) environments using the Bayesian nonparametric (BNP) method. From the probability distribution of CGR and some input parameters, such as yield stress of irradiated material (
), stress intensity factor (
), electrochemical corrosion potential (ECP), and fast neutron fluence, the mean CGR is estimated and compared with the measured CGR. The analytical results show good reproducibility of the measured CGR. The results also indicate the possible neutron fluence effects on CGR in high CGR region (i.e., high neutron fluence condition) by radiation-induced segregation (RIS), localized deformation, and/or other mechanisms than radiation hardening.
Watanabe, Osamu*; Oyama, Kazuhiro*; Endo, Junji*; Doda, Norihiro; Ono, Ayako; Kamide, Hideki; Murakami, Takahiro*; Eguchi, Yuzuru*
Journal of Nuclear Science and Technology, 52(9), p.1102 - 1121, 2015/09
Times Cited Count：16 Percentile：73.31(Nuclear Science & Technology)A natural circulation (NC) evaluation methodology has been developed to ensure the safety of a sodium-cooled fast reactor (SFR) of 1500MW adopting the NC decay heat removal system (DHRS). The methodology consists of a 1D safety analysis which can evaluate the core hot spot temperature taking into account the temperature flattening effect in the core, a 3D fluid flow analysis which can evaluate the thermal-hydraulics for local convections and thermal stratifications in the primary system and DHRS, and a statistical safety evaluation method. The safety analysis method and the 3D analysis method have been validated using results of a 1/10 scaled water test simulating the primary system of the SFR and a 1/7 scaled sodium test simulating the primary system and the DHRS, and the applicability of the safety analysis for the SFR has been confirmed by comparing with the 3D analysis. Finally, a statistical safety evaluation has been performed for the SFR using the safety analysis method.
; ; Takasaki, Koichi*; ;
JAERI-Review 98-005, 203 Pages, 1998/03
JAERI-Review-98-005.pdf:8.96MB
no abstracts in English
; ; ; ; ;
Nuclear Safeguards Technology 1986,Vol.1, p.341 - 352, 1987/00
no abstracts in English
J.Lovett*; ; J.Shipley*; D.Sellinschegg*
J.Inst.Nucl.Mater.Manage., 12, p.31 - 34, 1983/00
no abstracts in English
J.Lovett*; ; J.Shipley*; D.Selliuschegg*
Nuclear Safeguards Technology,Vol.1, p.487 - 497, 1982/00
no abstracts in English
; ; ; ; ;
JAERI-M 9665, 143 Pages, 1981/10
no abstracts in English
J.E.Lovett*; ; ; R.H.Augustson*
JAERI-M 9186, 46 Pages, 1980/11
no abstracts in English
; ;
JAERI-M 8757, 41 Pages, 1980/03
no abstracts in English
; Osamu Tanaka*
Journal of the Physical Society of Japan, 18(5), p.610 - 619, 1963/00
Times Cited Count：13no abstracts in English
Ueki, Taro
no journal, ,
A new methodology has been developed to make the reliable estimation of statistical errors in Monte Carlo criticality calculation (MCCC). The methodology developed is directly based on the convergence process in the functional central limit theorem and is shown to perform well in the evaluation of reactor power distribution. The theoretical backbones are described within the general context as framed in the operations research. The requisite basics of statistics are reviewed in terms of output analysis in MCCC. Numerical results are presented for the initial core model of a 1200 MWe pressurized water reactor. Preliminary results of fractal dimension analysis are shown to discuss a potential for convergence assessment.
