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Nakayama, Shinichi; Okumura, Masahiko*; Nagasaki, Shinya*; Enokida, Yoichi*; Umeki, Hiroyuki*; Takase, Hiroyasu*; Kawasaki, Daisuke*; Hasegawa, Shuichi*; Furuta, Kazuo*
Genshiryoku Bakkuendo Kenkyu (CD-ROM), 23(2), p.131 - 148, 2016/12
A symposium "Science of nuclear fuel cycle and backend - Research and education -" was held at the Univer-sity of Tokyo in June 25, 2016. This aimed at developing the research on nuclear fuel cycle and backend. The time and the number of participants of the symposium were limited, but the active discussion was conducted, and the common perception for the future was shared among the experienced participants in those fields. This paper provides the discussions made in the symposium, and also, as a memory to Professor Ahn, the University of California, Berkeley, his prominent achievements in academic research and education.
Omori, Kazuaki; Munemoto, Takashi; Hasegawa, Takashi; Shingu, Shinya*; Hagiwara, Hiroki; Iwatsuki, Teruki
JAEA-Research 2014-013, 29 Pages, 2014/08
JAEA-Research-2014-013.pdf:48.04MB
We summarized investigation method of colloid in groundwater. We examined the ultrafiltration of groundwater by using in-situ water monitoring system and batch type airtight container. Additionally, we examined the cross flow filtration method replaced by ultrafiltration. The knowledge of investigating methods is obtained.
Shibanuma, Kiyoshi; Arai, Takashi; Hasegawa, Koichi; Hoshi, Ryo; Kamiya, Koji; Kawashima, Hisato; Kubo, Hirotaka; Masaki, Kei; Saeki, Hisashi; Sakurai, Shinji; et al.
Fusion Engineering and Design, 88(6-8), p.705 - 710, 2013/10
Times Cited Count：12 Percentile：61.84(Nuclear Science & Technology)Matsuo, Yoichiro; Hasegawa, Masanori; Maegawa, Yoshiharu; Miyahara, Shinya
Hoken Butsuri, 46(4), p.304 - 313, 2011/12
Radioactive corrosion products (CP) are main source of personal radiation exposure during maintenance without fuel-failure accident in the liquid-metal fast breeder reactor (LMFBR) plants. In order to establish the techniques of radiation dose estimation for personnel, program system DORE has been developed. The DORE system is constructed by PSYCHE code and QAD code system. The density of each deposited CP of primary coolant system in MONJU was estimated by using the PSYCHE. Moreover, the QAD-CGGP2R code is applied to dose rate calculations for the primary coolant system in MONJU. The predicted values were estimated to be saturated at 2-3 mSv/h in twenty years after the start of operation, and the dose rate reaches 4 mSv/h in domains near the IHX and the cold-leg piping.
Matsuo, Yoichiro; Hasegawa, Masanori; Maegawa, Yoshiharu; Miyahara, Shinya
Journal of Power and Energy Systems (Internet), 5(1), p.96 - 107, 2011/01
Radioactive corrosion products (CP) are primary cause of personal radiation exposure during maintenance work at FBR plants with no breached fuel. The PSYCHE code has been developed based on the solution-precipitation model for analysis of CP transfer behavior. We predicted and analyzed the CP solution and precipitation behavior of MONJU to evaluate the applicability of the PSYCHE code to MONJU, using the parameters verified in the calculations for JOYO. From the calculation result pertaining to the MONJU system, distribution of 
Mn deposited in the primary cooling system over 20 years of operation is predicted to be approximately 7 times larger than that of 
Co. In particular, predictions show a notable tendency for Mn precipitation to be distributed in the primary pump and cold-leg. The calculated distribution of Mn and Co in the primary cooling system of MONJU agreed with tendencies of measured distribution of JOYO.
Matsuo, Yoichiro; Hasegawa, Masanori; Maegawa, Yoshiharu; Miyahara, Shinya
Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 8 Pages, 2010/05
Radioactive corrosion products are main cause of personal radiation exposure during maintenance with no breached fuel in FBR plants. CP is produced in the core region by activation of fuel cladding and sub-assembly wrappers, and they are transported to the primary circuit with sodium flow and deposited on the wall of the primary piping and components. In order to establish the techniques of radiation dose reduction for of personnel, program system for corrosion hazard evaluation code PSYCHE has been was developed. The PSYCHE code is based on the solution-precipitation model. The density of each deposited CP and dose rate of primary coolant system in Monju was estimated by using the PSYCHE and QAD-CG code.
Azumi, Masafumi; Hasegawa, Mitsuru*; ; Kurihara, Kenichi; Nakamura, Yukiharu; Nishio, Satoshi; Shimomura, Yasuo; Shinya, K.*; Sugihara, Masayoshi; ; et al.
JAERI-M 92-041, 100 Pages, 1992/03
no abstracts in English
; ; ; Ando, Toshinari; Fujisawa, Noboru; Hasegawa, Mitsuru*; ; ; ; Iida, Hiromasa; et al.
JAERI-M 88-010, 206 Pages, 1988/02
no abstracts in English
Matsuo, Yoichiro; Hasegawa, Masanori; Maegawa, Yoshiharu; Miyahara, Shinya
no journal, ,
In order to reduce the personal radiation exposure during maintenance, the CPs transport behavior analysis code "PSYCHE" has been developed. The density of each deposited CP of primary coolant system in MONJU was estimated by using the PSYCHE. Moreover, the calculation result in the case that PNC and T-T equation for corrosion rate was compared. Our results suggest that the down stream effect was important in the cobalt type.
Asahi, Yuichi; Maeyama, Shinya*; Bigot, J.*; Garbet, X.*; Grandgirard, V.*; Fujii, Keisuke*; Shimokawabe, Takashi*; Watanabe, Tomohiko*; Idomura, Yasuhiro; Onodera, Naoyuki; et al.
no journal, ,
We have established an in-situ data analysis method for large scale fluid simulation data and developed deep learning based surrogate models to predict fluid simulation results. Firstly, we have developed an in-situ data processing approach, which loosely couples the MPI application and python scripts. It has been shown that this approach is simple and efficient which offers the speedup of 2.7 compared to post hoc data processing. Secondly, we have developed a deep learning model for predicting multiresolution steady flow fields. The deep learning model can give reasonably accurate predictions of simulation results with orders of magnitude faster compared to simulations.
Taneichi, Yayoi; Amano, Yuki; Mochizuki, Akihito; Yokoyama, Tatsunori; Kagami, Saya; Hasegawa, Shinya*; Kubota, Mitsuru*; Ouchi, Yuji*; Ishidera, Takamitsu
no journal, ,
no abstracts in English
Hasegawa, Koichi; Arai, Takashi; Hoshi, Ryo; Masaki, Kei; Saeki, Hisashi; Sakata, Shinya; Sawai, Hiroaki; Shibanuma, Kiyoshi; Suzuki, Sadaaki; Tsukao, Naohiro; et al.
no journal, ,
JAEA pushes forward construction of superconduction tokamak (JT-60SA) as part of Broader Approach activity in cooperation with EU. JT-60SA is concentrated and highly precise with a large structure in the limited space, and it is necessary to assemble it. Therefore, from 2007, assembling examination using the 3D CAD has been performed. By this lecture introduce the examination situation of the assembling procedures such as TF coil, a vacuum vessel, cryostat, EF coil of JT-60SA.
Asahi, Yuichi; Maeyama, Shinya*; Bigot, J.*; Garbet, X.*; Grandgirard, V.*; Obrejan, K.*; Padioleau, T.*; Fujii, Keisuke*; Shimokawabe, Takashi*; Watanabe, Tomohiko*; et al.
no journal, ,
We will demonstrate the performance portable implementation of a kinetic plasma code over CPUs, Nvidia and AMD GPUs. We will also discuss the performance portability of the code with C++ parallel algorithm. Deep learning based surrogate models for fluid simulations will also be demonstrated.
Hasegawa, Shin; Azami, Shinya*; Sawada, Shinichi; Hino, Satoshi*; Isobe, Shigehito*; Hashimoto, Naoyuki*; Maekawa, Yasunari
no journal, ,
Hydrogen permselective membranes, which have high hydrogen permeability (approximately 10
10
mol/(m
s Pa) with selectivity against water and nitrogen, have been developed by radiation-induced graft polymerization (RIGP) of an acrylic acid (AAc), tetramethoxysirylstyrene (TMSS), and styrene(St) monomers into porous poly(vinylidene fluoride) (PVDF) films. The porosity of the prepared porous grafted PVDF were almost constant against grafting degrees. Thus, by hot press compression, the porosity of the grafted membranes was reduced to a 20-40% level. The hydrogen permeability of the compressed grafted PVDF is 10 10 mol/(m s Pa) with the hydrogen permselectivity of 3.2 and 3.5 against water and nitrogen, respectively. The above results indicate that RIGP of porous films with a hot press process is a very effective method to prepare hydrogen permselective membranes.
Yamada, Tomonori; Ishizuka, Ippei*; Takebe, Toshihiko*; Hanari, Toshihide; Omori, Shinya*; Kurosawa, Koichi*; Sasaki, Go*; Nakada, Masahiro*; Sakai, Hideaki*; Shibata, Takuya; et al.
no journal, ,
no abstracts in English
Asahi, Yuichi; Maeyama, Shinya*; Bigot, J.*; Garbet, X.*; Grandgirard, V.*; Obrejan, K.*; Padioleau, T.*; Fujii, Keisuke*; Shimokawabe, Takashi*; Watanabe, Tomohiko*; et al.
no journal, ,
We will demonstrate the performance portable implementation of a kinetic plasma code over CPUs, Nvidia and AMD GPUs. We will also discuss the performance portability of the code with C++ parallel algorithm. Deep learning based surrogate models for fluid simulations will also be demonstrated.
