Development of ARKADIA for the innovation of advanced nuclear reactor design process (Overview of optimization process development in design optimization support tool, ARKADIA-Design)

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

https://doi.org/10.1299/jsmepes.2022.26.A221

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.

Development of radiation resistant monitoring camera system

Takeuchi, Tomoaki; Otsuka, Noriaki; Watanabe, Takashi*; Tanaka, Shigeo*; Ozawa, Osamu*; Komanome, Hirohisa*; Ueno, Shunji*; Tsuchiya, Kunihiko

Proceedings of 2017 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC 2017) (Internet), 3 Pages, 2018/11

https://doi.org/10.1109/NSSMIC.2017.8532790

no abstracts in English

Electrooxidation of hydrazine hydrate using Ni-La catalyst for anion exchange membrane fuel cells

Sakamoto, Tomokazu*; Asazawa, Koichiro*; Martinez, U.*; Halevi, B.*; Suzuki, Toshiyuki*; Arai, Shigeo*; Matsumura, Daiju; Nishihata, Yasuo; Atanassov, P.*; Tanaka, Hirohisa*

Journal of Power Sources, 234, p.252 - 259, 2013/07

https://doi.org/10.1016/j.jpowsour.2013.01.181

Consideration on the earthquake-resistant margin of equipment base-bolts receiving the shearing load during seismic movements

Sakaguchi, Shinobu; Tachibana, Ikuya; Koshino, Katsuhiko; Shirozu, Hidetomo; Shirai, Nobutoshi; Imamoto, Nobuo; Tomita, Tsuneo; Tobita, Hiroo; Yamanaka, Atsushi; Kobayashi, Daisuke; et al.

JAEA-Technology 2011-006, 24 Pages, 2011/03

JAEA-Technology-2011-006.pdf:3.07MB

In the Niigataken Chuetsu-oki Earthquake on 2007, observed earthquake motion exceeded design base at the Kashiwazaki Kariwa nuclear plant. However, there was no earthquake damage in safety important equipments to stop reactor, to cool reactor, and to contain radioactive materials. One of this reason is said that many safety margin are included in the design and the permissible value. To know more accurate safety margin, shearing force examinations for the base bolts were conducted. In examinations, delegate test-bolts were made; the test bolts were selected from heavier equipment in Tokai Reprocessing Plant. In this report, the shearing strength obtained from the examinations shows more accurate safety margin.

Determination of trace amounts of uranium by stripping voltammetry using a boron-doped diamond electrode

Taguchi, Shigeo; Surugaya, Naoki; Kurosawa, Akira; Hiyama, Toshiaki; Tanaka, Tatsuhiko*

Bunseki Kagaku, 59(11), p.1035 - 1041, 2010/11

https://doi.org/10.2116/bunsekikagaku.59.1035

no abstracts in English

Rapid determination of trace uranium in liquid wastes from spent nuclear-fuel reprocessing plants using on-line solid-phase extraction / electrochemical detection

Taguchi, Shigeo; Surugaya, Naoki; Kurosawa, Akira; Hiyama, Toshiaki; Tanaka, Tatsuhiko*

Bunseki Kagaku, 58(10), p.901 - 907, 2009/10

https://doi.org/10.2116/bunsekikagaku.58.901

An on-line analysis system using a solid-phase extraction column coupled to electrochemical detection has been developed for rapid determination of small amounts of uranium in liquid wastes of spent nuclear-fuel reprocessing plants. A sample solution with a concentration of 3 M HNO was loaded onto the column: packed with U/TEVA resin. The interference elements were rinsed by passing 3 M HNO through the column. The adsorbed uranium was eluted with 0.1 M HNO. The eluate was directly introduced into a flow-electrolysis cell. The result of five repeated analyses for a standard solution containing 2.5 g (0.1 mL at 25 g mL) of uranium was found to be 2.5 0.025 g (mean 1 ). The detection limit calculated from 3 times the standard deviation of background current was 56 ng. The analysis time required for one sample was within 5 min. The recoveries of uranium in actual nuclear waste reprocessing solutions were 92% 112%.

The Prospective role of JAEA Nuclear Fuel Cycle Engineering Laboratories

Ojima, Hisao; Dojiri, Shigeru; Tanaka, Kazuhiko; Takeda, Seiichiro; Nomura, Shigeo

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.273 - 282, 2007/09

The Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency (JAEA) was established to take over activities of the Tokai Works of Japan Nuclear Cycle Development Institute (JNC). From 1959, several kinds of technologies (such as uranium refining, centrifuge for uranium enrichment, LWR spent fuel reprocessing and MOX fuel fabrication) have been accomplished. And also, R&Ds on the treatment and disposal of high level waste and the FBR fuel reprocessing have been carried out. Through such activities, control of environmental release of radioactive material and radiation exposure and management of nuclear materials have been done appropriately. The Laboratories will contribute to establish the closed cycle with R&Ds of the reprocessing technology during the transition period from LWR era to FBR era, improved MOX fuel fabrication technology, advanced FBR fuel reprocessing technology and high level waste disposal technology.

Degradation of charge collection efficiency obtained for 6H-SiC np diodes irradiated with gold ions

Oshima, Takeshi; Sato, Takahiro; Oikawa, Masakazu; Onoda, Shinobu; Hishiki, Shigeomi; Hirao, Toshio; Kamiya, Tomihiro; Yokoyama, Takuro*; Sakamoto, Airi*; Tanaka, Reisaburo*; et al.

Materials Science Forum, 556-557, p.913 - 916, 2007/00

https://doi.org/10.4028/www.scientific.net/MSF.556-557.913

no abstracts in English

Development of minor actinide containing fuel/target for the use in a future integrated system of fast reactor and accelerator driven system

Osaka, Masahiko; Serizawa, Hiroyuki*; Kato, Masato; Inoue, Masaki; Nakajima, Kunihisa*; Tachi, Yoshiaki; Kitamura, Ryoichi; Oki, Shigeo; Miwa, Shuhei; Iwai, Takashi*; et al.

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

Development of minor actinide containing fuel/target, i.e., (Pu,Am)O-MgO, (Pu,Np)O-MgO, (U,Pu,Np)O, (U,Pu,Np)N and (Pu,Np,Zr)N, for the use in a future integrated system of fast reactor and accelerator driven system is underway as a collaborative work between JAERI and JNC. The present statuses of fabrication test and property measurements are given. Irradiation test in the experimental fast reactor JOYO is also mentioned.

D-T neutron skyshine experiments and the MCNP analysis

Nishitani, Takeo; Ochiai, Kentaro; Yoshida, Shigeo*; Tanaka, Ryohei*; Wakisaka, Masashi*; Nakao, Makoto*; Sato, Satoshi; Yamauchi, Michinori*; Hori, Junichi; Wada, Masayuki*; et al.

Journal of Nuclear Science and Technology, 41(Suppl.4), p.58 - 61, 2004/03

http://www.tandfonline.com/doi/abs/10.1080/00223131.2004.10875644

no abstracts in English