Validation of evaluation model for analysis of steam reformer in HTGR hydrogen production plant

Ishii, Katsunori; Aoki, Takeshi; Isaka, Kazuyoshi; Noguchi, Hiroki; Shimizu, Atsushi; Sato, Hiroyuki

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 9 Pages, 2023/05

Development plan for coupling technology between high temperature gas-cooled reactor HTTR and Hydrogen Production Facility, 2; Development plan for coupling equipment between HTTR and Hydrogen Production Facility

Mizuta, Naoki; Morita, Keisuke; Aoki, Takeshi; Okita, Shoichiro; Ishii, Katsunori; Kurahayashi, Kaoru; Yasuda, Takanori; Tanaka, Masato; Isaka, Kazuyoshi; Noguchi, Hiroki; et al.

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 6 Pages, 2023/05

Study in the sedimentary processes of organic matter in the Pliocene to Miocene siliceous rocks in the Horonobe district, northern Hokkaido, Japan

Muraoka, Ami*; Chiyonobu, Shun*; Arato, Hiroyuki*; Martizzi, P.*; Ishii, Eiichi

Sekiyu Gijutsu Kyokai-shi (CD-ROM), 87(1), p.86 - 88, 2022/00

no abstracts in English

Optimum temperature for HIP bonding invar alloy and stainless steel

Wakui, Takashi; Ishii, Hideaki*; Naoe, Takashi; Kogawa, Hiroyuki; Haga, Katsuhiro; Wakai, Eiichi; Takada, Hiroshi; Futakawa, Masatoshi

Materials Transactions, 60(6), p.1026 - 1033, 2019/06

https://doi.org/10.2320/matertrans.M2018346

The mercury target has large size as 1.31.32.5 m. In view of reducing the amount of wastes, we studied the structure so that the fore part could be separated. The flange is required to have high seal performance less than 110 Pa m/s. Invar with low thermal expansion is a candidate. Due to its low stiffness, however, the flange may deform when it is fastened by bolts. Practically invar is reinforced with stainless steel where all interface between them has to be bonded completely with the HIP bonding. In this study, we made specimens at four temperatures and conducted tensile tests. The specimen bonded at 973 K had little diffusion layer, and so fractured at the interface. The tensile strength reduced with increasing the temperature, and the reduced amount was about 10% at 1473 K. The analyzed residual stresses near the interface increased by 50% at maximum. Then, we concluded that the optimum temperature was 1173 K.

Numerical evaluation on fluctuation absorption characteristics based on nuclear heat supply fluctuation test using HTTR

Takada, Shoji; Honda, Yuki*; Inaba, Yoshitomo; Sekita, Kenji; Nemoto, Takahiro; Tochio, Daisuke; Ishii, Toshiaki; Sato, Hiroyuki; Nakagawa, Shigeaki; Sawa, Kazuhiro*

Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 7 Pages, 2018/10

Nuclear heat utilization systems connected to HTGRs will be designed on the basis of non-nuclear grade standards for easy entry of chemical plant companies, requiring reactor operations to continue even if abnormal events occur in the systems. The inventory control is considered as one of candidate methods to control reactor power for load following operation for siting close to demand area, in which the primary gas pressure is varied while keeping the reactor inlet and outlet coolant temperatures constant. Numerical investigation was carried out based on the results of nuclear heat supply fluctuation tests using HTTR by non-nuclear heating operation to focus on the temperature transient of the reactor core bottom structure by imposing stepwise fluctuation on the reactor inlet temperature under different primary gas pressures below 120C. As a result, it was emerged that the fluctuation absorption characteristics are not deteriorated by lowering pressure. It was also emerged that the reactor outlet temperature did not reach the scram level by increasing the reactor inlet temperature 10 C stepwise at 80% of the rated power as same with the full power case.

Fine dispersion of Pt subnanoclusters and Pt single atoms over porous carbon supports and their structural analyses with X-ray absorption spectroscopy

Itoi, Hiroyuki*; Nishihara, Hirotomo*; Kobayashi, Shunsuke*; Ittisanronnachai, S.*; Ishii, Takafumi*; Berenguer, R.*; Ito, Masashi*; Matsumura, Daiju; Kyotani, Takashi*

Journal of Physical Chemistry C, 121(14), p.7892 - 7902, 2017/04

https://doi.org/10.1021/acs.jpcc.7b00422

Development of a measurement system for the determination of () cross-sections using multi-nucleon transfer reactions

Makii, Hiroyuki; Ota, Shuya*; Ishii, Tetsuro; Wakabayashi, Yasuo*; Furutaka, Kazuyoshi; Nishio, Katsuhisa; Nishinaka, Ichiro; Chiba, Satoshi; Igashira, Masayuki*; Czeszumska, A.*

Nuclear Instruments and Methods in Physics Research A, 797, p.83 - 93, 2015/10

https://doi.org/10.1016/j.nima.2015.05.005

We have installed new experimental apparatus to measure rays from highly excited states populated by the multi-nucleon transfer reactions with heavy-ion projectiles to determine the () cross sections by means of the surrogate reaction method. Apparatus consists of two anti-Compton LaBr(Ce) spectrometers to measure the rays and a Si - detector system to detect outgoing projectile-like particles. Reactions of 153-MeV O beams with Gd and Gd targets were used to study the performance of apparatus. By using the LaBr(Ce) scintillators with relatively large volume (101.6 mm in diameter and 127 mm in length), we have successfully measured rays from the compound nuclei, which have excitation energy above neutron separation energy, populated by Gd(O, O)Gd and Gd(O, O)Gd two-neutron transfer reactions. The present study has demonstrated high capability of apparatus to measure the de-excitation rays in the compound nuclei produced by the multi-nucleon transfer reactions for determination of the () cross sections by using the surrogate reaction method.

Effect of stability of passive film on resistance of rust staining of stainless steels

Fuji, Hiroyuki*; Aoki, So; Ishii, Tomohiro*; Sakai, Junichi*

Zairyo To Kankyo, 64(5), p.178 - 182, 2015/05

https://doi.org/10.3323/jcorr.64.178

This study focused on a breakdown of passive film which is followed by rust staining, and the objective of this study was to clarify the effect of stability of passive film on the resistance of rust staining of stainless steels. Atomospheric exposure test was carried out for 12 months. In order to compare the stability of passive film, measurements of potential-decay curves, and potentiostatic polarization tests were performed in acidic aqueous chloride solution. As a result, rust area of austenitic stainless steel was higher than that of ferritic stainless steel. This order didn't follow the orders of pitting potentials and densities of inclusions on surface between specimens. On the contrary, the order of the resistance of rust staining of stainless steels followed the order of the stability of passive film. One of the reasons why the resistance of rust staining of austenitic stainless steel was worse than that of ferritic stainless steel was seemed that chloride more easily broke passive film on the surface of austenitic stainless and formed micro pits which become initiations of rust staining and increase density of stains.

Effects of glutathione concentration in the root zone and glutathione treatment period on cadmium partitioning in oilseed rape plants

Nakamura, Shinichi*; Kondo, Hikari*; Suzui, Nobuo; Yin, Y.-G.; Ishii, Satomi; Kawachi, Naoki; Rai, Hiroki*; Hattori, Hiroyuki*; Fujimaki, Shu

Molecular Physiology and Ecophysiology of Sulfur, p.253 - 259, 2015/00

https://doi.org/10.1007/978-3-319-20137-5_28

A Study on the method of an equivalent continuous body modelling using crack tensor theory in the Mizunami Underground Research Laboratory Project

Sanada, Hiroyuki; Sato, Toshinori; Tanno, Takeo*; Hikima, Ryoichi*; Tada, Hiroyuki*; Kumasaka, Hiroo*; Ishii, Takashi*; Sakurai, Hideyuki*

JAEA-Research 2014-006, 124 Pages, 2014/06

JAEA-Research-2014-006.pdf:11.26MB

Japan Atomic Energy Agency has been implementing the Mizunami Underground Research Laboratory (MIU) Project in order to develop the comprehensive investigation techniques for the geological environment and the engineering techniques to construct a deep underground laboratory in crystalline rock. In the rock mechanical study in the MIU Project, the development of the evaluation method for the excavation damaged zone due to excavation of shafts and research galleries is one of the important issues. In this report, crack tensor was calculated using the tunnel wall mapping and rock mechanical test results in the shaft and research galleries in the MIU. Two dimension excavation analysis was conducted at the Ventilation Shaft and GL -500 m Sub Stage using the calculated crack tensor at GL -500 m. Based on calculated crack tensor at GL 500 m, validation of the crack tensor at GL -500 m estimated during Phase I was verified. Relative error of crack tensor was calculated in order to examine variation of relative error to the scale of observation areas.