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Kikuchi, Norihiro; Mori, Takero; Okajima, Satoshi; Tanaka, Masaaki; Miyazaki, Masashi
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 8 Pages, 2023/05
JAEA is developing an evaluation system aided by artificial intelligence (AI) named ARKADIA (Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle). A sub-system of it, named ARKADIA-Design, is being developed to support the design optimization study for an advanced nuclear plant including a sodium-cooled fast reactor (SFR). Authors are developing a design optimization process for the structure of the component in SFR. This paper describes the outline of a design optimization process, the brief introduction of evaluation methods for the process, and the result of the demonstration of the optimization process for a feasibility study. The development is being performed in a representative problem considering the thermal transient and seismic motion as a major issue in SFRs. Through the demonstration, it was confirmed that the optimization process under development may provide an optimal solution to the representative problem.
Kikuchi, Norihiro; Mori, Takero; Okajima, Satoshi; Tanaka, Masaaki; Miyazaki, Masashi
Dai-26-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2022/07
In JAEA, the design optimization method for plant structure has been developed on the process to output optimal solution of the thickness of reactor vessel wall against thermal transient and seismic loads in a SFR as a representative problem. Resistance characteristic of the wall on the load derived from thermal transient is one of the most important factors for safety estimation on the structural integrity. Failure probability of components against thermal transient was set to one of variables in the objective function for a common scale to compare with other variables in different failure mechanisms. In the iterative process to achieve the optimal solution, a number of evaluations to measure the influence on the load derived from thermal transient was necessarily conducted. More reduction of required time for evaluations is desired. To perform the iterative evaluation process efficiently, the automatization of parametric analyses was implemented in the optimization process.
Tanaka, Masaaki; Doda, Norihiro; Yokoyama, Kenji; Mori, Takero; Okajima, Satoshi; Hashidate, Ryuta; Yada, Hiroki; Oki, Shigeo; Miyazaki, Masashi; Takaya, Shigeru
Dai-26-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2022/07
To assist conceptual studies of various reactor systems conducted by private sectors in nuclear power innovation, development of an innovative design system named ARKADIA (Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle) is undergoing to achieve the design of an advanced nuclear reactor as a safe, economic, and sustainable carbon-free energy source. In this paper, focusing on the ARKADIA-Design as a part of it, the progress in the development of optimization processes on the representative problems in the fields of the core design, the plant structure design, and the maintenance schedule planning are introduced.
Ando, Masami; Wakai, Eiichi; Sawai, Tomotsugu; Matsukawa, Shingo; Naito, Akira*; Jitsukawa, Shiro; Oka, Keiichiro*; Tanaka, Teruyuki*; Onuki, Somei*
JAERI-Review 2004-025, TIARA Annual Report 2003, p.159 - 161, 2004/11
The objectives of this study are to evaluate radiation hardening on ion-irradiated F82H up to 100 dpa and to examine the extra component of radiation hardening due to implanted helium atoms (up to 
3000 appmHe) in F82H under ratio of 0, 10, 100 appmHe/dpa.The ion-beam irradiation experiment was carried out at the TIARA facility of JAERI. Specimens were irradiated at 633 K by 10.5 MeV Fe ions with/without 1.05 MeV He ions. Micro-indentation tests were performed at loads to penetrate about 0.40 mm in the irradiated specimens using an UMIS-2000. The results are summarized as follows:1) As a result of the single irradiated F82H, the micro-hardness tended to increase about 30 dpa. 2) The extra radiation hardening was obviously caused by co-implanted helium atoms more than 1000 appm in F82H irradiated at 633 K. 3) In the dual-beam (100 appmHe/dpa) irradiated microstructure, nano-voids and fine defects were observed. It is suggested that the formation of nano-voids causes the extra radiation hardening by helium co-implantation.
Shiba, Kiyoyuki; Enoeda, Mikio; Jitsukawa, Shiro
Journal of Nuclear Materials, 329-333(Part1), p.243 - 247, 2004/08
Times Cited Count：53 Percentile：94.45(Materials Science, Multidisciplinary)no abstracts in English
Ando, Masami; Tanigawa, Hiroyasu; Jitsukawa, Shiro; Sawai, Tomotsugu; Kato, Yudai*; Koyama, Akira*; Nakamura, Kazuyuki; Takeuchi, Hiroshi
Journal of Nuclear Materials, 307-311(Part1), p.260 - 265, 2002/12
Times Cited Count：39 Percentile：90.08(Materials Science, Multidisciplinary)no abstracts in English
Seki, Masahiro; Tsuji, Hiroshi; Ohara, Yoshihiro; Akiba, Masato; Okumura, Yoshikazu; Imai, Tsuyoshi; Nishi, Masataka; Koizumi, Koichi; Takeuchi, Hiroshi
Fusion Technology, 39(2-Part.2), p.367 - 373, 2001/03
no abstracts in English
Oda, Tomomasa*; Hirohata, Yuko*; Hino, Tomoaki*; Sengoku, Seio
Shinku, 43(3), p.325 - 328, 2000/03
no abstracts in English
Tsukada, Takashi
Materials for Advanced Energy Systems & Fission and Fusion Engineering '94, 0, p.466 - 471, 1994/00
no abstracts in English
Tsutani, Sadahiro*; Takeshita, Hiroshi*; Edajima, Toshikazu*; Motooka, Masafumi*
PNC TJ8224 93-001, 128 Pages, 1993/06
no abstracts in English
; *; Iida, Hiromasa;
Genshiryoku Kogyo, 38(4), p.55 - 60, 1992/04
no abstracts in English
Shibanuma, Kiyoshi; *; *; *; Okawa, Yoshinao; *; Tada, Eisuke; Koizumi, Koichi; *; Nishio, Satoshi; et al.
JAERI-M 91-080, 357 Pages, 1991/06
no abstracts in English
; Takahashi, Takeshi
PNC TN8410 91-158, 19 Pages, 1991/04
Joule heated ceramic melter has been developed to vitrify high-level liquid wastes (HLLW) from reprocessing nuclear spent fuel at Power Reacter and Nuclear Fuel Development Corporation (PNC). Noble metal elements such as ruthenium, paladium and rhodium are contained as fission products in the HLLW. The operational chracteristics of Joule-heated ceramic melter were studied on the effects of these elements. Two small scale melters with sloped floor were fabricated and tested. The slope was 30
and 45 for each. The operational characteristics including electrode resistance, temperature profile etc. were monitored. The drain efficiency of noble metal elements from the melters during the glass drain operation were evaluated. After the test operation, the melters were cut after cooled with the glass left in the melting cavities, following the termination of the test operations. The sediments of the precipitations of the noble metal elements were evaluated from the sectional observation for the melter. The results from the studies were compared between 30 and 45 slopes and discussed. It was concluded that the 45 sloped floor was clearly effective to drain the noble metal elements and the structure of the 45 sloped floor melter was compatible with some amount of precipitates at the bottom.
Kimura, Hidetaka; *; *; Kawasaki, Hirotsugu; Aoto, Kazumi;
PNC TN9450 91-003, 28 Pages, 1991/03
None
Kondo, Tatsuo
Purometeusu, 0(67), p.34 - 38, 1988/00
no abstracts in English
Tone, Tatsuzo; ; *; *; *; *
JAERI-M 83-031, 157 Pages, 1983/03
no abstracts in English
; Tone, Tatsuzo; ; ; *; *; *; *; *; *; et al.
JAERI-M 8286, 108 Pages, 1979/06
no abstracts in English
JAERI-M 7300, 545 Pages, 1977/09
no abstracts in English
;
Nihon Genshiryoku Gakkai-Shi, 9(7), p.411 - 418, 1967/00
no abstracts in English
Tobita, Kenji
no journal, ,
Status of DEMO design conducted under the Broader Approach Activity is reported highlighting on Japanese design activity. Remote maintenance is one of the most critical design issues in DEMO in that a reasonable plant availability needs to be attained in severe radiation environment. Recent design study revealed that the application of "sector maintenance" scheme to a medium size DEMO with a major radius of about 8 m would lead to increase in the size of toroidal field coils, the required current of poloidal field coils and the sector weight. For this reason, "banana-type segment" scheme is under study instead of the sector scheme. In order to resolve diverter heat removal problem, use of copper alloy pipes in high heat flux and low dpa (displacements per atom) zones is under study. Besides, a possible management scenario of radioactive waste produced in periodic maintenance and the resulting waste-related facilities for DEMO are presented.
