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Iwasawa, Hideaki*; Sumida, Kazuki; Ishida, Shigeyuki*; Le Fvre, P.*; Bertran, F.*; Yoshida, Yoshiyuki*; Eisaki, Hiroshi*; Santander-Syro, A.*; Okuda, Taichi*
Scientific Reports (Internet), 13, p.13451_1 - 13451_7, 2023/08
Saito, Kimiaki; Mikami, Satoshi; Ando, Masaki; Matsuda, Norihiro; Kinase, Sakae; Tsuda, Shuichi; Yoshida, Tadayoshi; Sato, Tetsuro*; Seki, Akiyuki; Yamamoto, Hideaki*; et al.
Journal of Environmental Radioactivity, 210, p.105878_1 - 105878_12, 2019/12
Times Cited Count:30 Percentile:81.17(Environmental Sciences)Matsumoto, Takashi; Morimoto, Yasuyuki; Takahashi, Nobuo; Takata, Masaharu; Yoshida, Hideaki; Nakashima, Shinichi; Ishimori, Yuu
JAEA-Technology 2015-036, 60 Pages, 2016/01
The Enrichment Engineering Facilities of the Ningyo-toge Environmental Engineering Center was constructed in order to establish the technical basis of the uranium enrichment plant in Japan. Uranium enrichment tests, using natural and reprocessed uranium, were carried out from 1979 to 1990 at two types of plants in the facilities. UF handling equipment and Supplemental equipment in these plants are intended to be dismantled by 2019 in order to make places for future projects, for example, inventory investigation, precipitation treatment, etc. This report shows the basic plan of this decommissioning project and presents the current state of dismantling in the first-half of the fiscal year of 2014, with indicating its schedule, procedure, situation, results, and so on. The dismantled materials generated amounted to 37 mesh containers and 199 drums, and the secondary waste generated amounted to 271.4 kg.
Kanda, Nobuhiro; Daiten, Masaki; Endo, Yuji; Yoshida, Hideaki; Mita, Yutaka; Naganawa, Hirochika; Nagano, Tetsushi; Yanase, Nobuyuki
JAEA-Technology 2015-007, 43 Pages, 2015/03
The centrifuge which has the subtlety information concerning the nuclear nonproliferation used for uranium enrichment technical development exists in the uranium enrichment facilities of Ningyo-toge Environmental Engineering Center, Japan Atomic Energy Agency. This centrifugal is performing separation processing of the radioactive material adhering to the surface of parts by wet decontamination of ultrasonic cleaning by dilute sulfuric acid and water, etc. By removing the uranium contained in waste fluid, generated sludge reduces activity concentration. And the possibility of reduction of sludge processing is examined. For this reason, from the 2007 fiscal year, Nuclear Science and Engineering Directorate and cooperation are aimed at, and development of the extraction separation technology of the "uranium" by the emulsion flow method is furthered. The test equipment using the developed emulsion flow method was tested. And dilute sulfuric acid and water were used for the examination as actual waste fluid. The result checked whether the various performances in Basic test carried out in Nuclear Science and Engineering Directorate would be obtained.
Yoshida, Tadayoshi; Tsujimura, Norio; Miyata, Hideaki*
Progress in Nuclear Science and Technology (Internet), 4, p.396 - 399, 2014/04
The authors performed the complementary work which determined the proportion of the contaminating photons present in the moderated neutron field using a Cf neutron source surrounded with the moderators. The measurements of the photon dose rates were performed by three instruments with different detection principles and the results were compared with the Monte Carlo calculation results. The contaminant photon dose rates observed from each instrument were in good agreement, and the measurement and calculation results also agreed well.
Maeda, Yukimoto; Aoyama, Takafumi; Yoshida, Akihiro; Sekine, Takashi; Ariyoshi, Masahiko; Ito, Chikara; Masaaki, Nemoto; Murakami, Takanori; Isozaki, Kazunori; Hoshiba, Hideaki; et al.
JNC TN9410 2003-011, 197 Pages, 2004/03
MK-III performance tests began in June 2003 to fully characterize the upgraded core and heat transfer system. Then, the last pre-use inspection was finished in November 2003.This report summarize the result of each performance test.
Suzuki, Hideaki*; Ito, Akira; Yoshida, Yasushi*; Suyama, Tadahiro*; Kawakami, Susumu; Sasamoto, Hiroshi; Yui, Mikazu
JNC TN8400 2003-033, 235 Pages, 2004/02
The research for numerical experiments on the coupled Thermo -Hydro -Mechanical and Chemical (THMC) processes in the near-field of a high-level radioactive waste repository has been initiated, in order to increase reality in the near-field environmental condition adopted in the evaluation of engineered barrier design and performance assessment.As a part of this research, experimental studies on the coupled THMC processes by COUPLE equipment have been carried out. The COUPLE equipment simulates the coupled processes in the near-field after emplacement of the engineered barrier. The specimen of COUPLE equipment is composed of heater, buffer material and mortar block. In this experiment, temperature at heater and side surface of mortar block was kept at 100 and 70C, respectively. And high-pH water reacted with mortar infiltrates into the buffer material.This report presents the results of measured data by embedded sensor (thermocouple, psychrometer, pressure transducer and pH meter etc.) during the experiment, and direct measurement of pH and water content of buffer material after the experiment.This report also presents the preliminary simulations, of coupled T-H processes, and of chemical process in mortar block and buffer material in the experiment.
Torimaru, Tadahiko; Yoshida, Akihiro; Nagasaki, Hideaki*; Suzuki, Soju
PNC TN9410 98-034, 31 Pages, 1998/03
Decay heat measurement system for the JOYO spent fuels was developed to obtain the decay heat data of the fuel assemblies as a non-destructive examination method. Since then, decay heat of the JOYO Mk-II fuels, which were cooled for more than 70 days, was measured in the spent fuel storage pond. The measurement of the short term cooled spent fuels, which were discharged without cooling in the reactor vessel, was performed in order to obtain the higher decay heat of the spent fuels. The burn-up of the measured fuels was about 60GWd/t, and the shortest cooling time was 24 days. The experimental data were compared with calculated values of ORIGEN2 using new libraries based on latest nuclear data library "JENDL-3.2". The main results are as follows; (1) The measured decay heat at 24 days after the reactor shut down was approximately 1.250.3 kW. (2) The ratio between calculated and experimental values, C/E, was approximately 0.9 and indicated a cool down time dependence. (3) The heat generated by Pu and Am, which amount to 1% of initial composition of fresh fuel, reached 7 - 19% of decay heat at 24-160 days after the reactor shut down.
Fukuda, Takeshi; Yoshida, Hidetoshi; Nagashima, Akira; Ishida, Shinichi; Kikuchi, Mitsuru; Yokomizo, Hideaki; JT-60 Team
Journal of Nuclear Materials, 162-164, p.258 - 263, 1989/00
Times Cited Count:2 Percentile:33.14(Materials Science, Multidisciplinary)no abstracts in English
Yokomizo, Hideaki; Yoshida, Hidetoshi; Sato, Masayasu; Nagashima, Akira; *; *
Kaku Yugo Kenkyu, 59(SPECIAL ISSUE), p.72 - 90, 1988/00
no abstracts in English
; ; ; ; Yoshida, H.; ; ; ; ; ; et al.
Nuclear Fusion, 27(8), p.1239 - 1244, 1987/08
Times Cited Count:13 Percentile:45.31(Physics, Fluids & Plasmas)no abstracts in English
; ; ; ; Yoshida, H.; ; ; ; ; ; et al.
JAERI-M 87-008, 25 Pages, 1987/02
no abstracts in English
; ; *; *; ; ; *; Yoshida, H.; N.H.Brooks*; C.L.Hsieh*; et al.
JAERI-M 9862, 23 Pages, 1981/12
no abstracts in English
; *; ; ; Yoshida, H.; *; *;
JAERI-M 9763, 21 Pages, 1981/10
no abstracts in English
; ; ; N.H.Brooks*; R.P.Seraydarian*; *; ; Yoshida, H.; *; *; et al.
JAERI-M 9698, 29 Pages, 1981/09
no abstracts in English