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JAEA Reports

In-situ dismantling of the liquid waste storage tank LV-1 in the JRTF; The Dismantling preparation work

Yokozuka, Yuta; Sunaoshi, Mizuho*; Fujikura, Toshiki; Suzuki, Shota; Muraguchi, Yoshinori; Handa, Yuichi; Mimura, Ryuji; Terunuma, Akihiro

JAEA-Technology 2020-017, 56 Pages, 2021/01


JAEA has dismantled equipment and instrument in the JAERI's Reprocessing Test Facility (JRTF) since 1996 as a part of its decommissioning. Starting in JFY 2007, in the annex building B which stored liquid waste generated in wet reprocessing tests, the liquid waste storage tank LV-1 installed in the LV-1 room of the first basement was dismantled with the in situ dismantling method. The dismantling preparation work is described in this report. Data on manpower, radiation control, and waste in the preparation work were collected, and its work efficiency was analyzed.

JAEA Reports

Maintenance of the Evaporator-II in Waste Treatment Facility No.2 (FY2015)

Handa, Yuichi; Nakajima, Ryota; Yonekawa, Akihisa*; Takatsu, Kazuki; Kinoshita, Junichi; Irie, Hirobumi; Suzuki, Hisao*

JAEA-Technology 2020-005, 22 Pages, 2020/06


The Evaporator-II is installed in Waste Treatment Facility No.2. The evaporator system treats intermediate level radioactive liquid waste for Nuclear Science Research Institute and more. It is maintenance the evaporator can once/3years by the maintenance plan. The evaporator can is important unit of the Evaporator-II system. This report summarizes record of maintenance the Evaporator-II in FY2015.

Journal Articles

A Suitable procedure for preparing of water samples used in radiocarbon intercomparison

Takahashi, Hiroshi*; Minami, Masayo*; Aramaki, Takafumi*; Handa, Hiroko*; Kokubu, Yoko; Ito, Shigeru*; Kumamoto, Yuichiro*

Radiocarbon, 61(6), p.1879 - 1887, 2019/12

 Times Cited Count:1 Percentile:13.83(Geochemistry & Geophysics)

Water sample for interlaboratory comparison (here after "comparison water") must have inalterable $$^{14}$$C concentration during the comparison campaign and inter-batches homogeneity. In this study, the procedure for preparing of comparison water was discussed. We employed that comparison waters were artificially made by mixing chemical reagents, controlling $$^{14}$$C concentration and chemical composition. We could prepare six comparison waters, having 1, 14, 37, 56, 72 and 100 pMC, respectively. The stable carbon isotopic values and chemical compositions of some batches were measured to exanimate the inter- batches homogeneity. The $$^{14}$$C discrepancies among the batches were negligible for the inter-laboratory comparison. Finally, the results of trial comparison in Japan will be presented. Most of $$^{14}$$C results of CO$$_{2}$$ extracted by six laboratories showed good agreements each other.

Journal Articles

Assessment of calculation model for annular core on the HTTR

Nojiri, Naoki; Handa, Yuichi*; Shimakawa, Satoshi; Goto, Minoru; Kaneko, Yoshihiko*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 5(3), p.241 - 250, 2006/09

It was shown from the annular core experiment of the HTTR that the discrepancy of excess reactivity between experiment and analysis reached about 3 % Dk/k at maximum. Sensitivity analysis for the annular core of the HTTR was performed to improve the discrepancy. The SRAC code system was used for the core analysis. As the results of the analysis, it was found clearly that the multiplication factor of the annular core is affected by (1) mesh interval in the core diffusion calculation, (2) mesh structure of graphite region in fuel lattice cell and (3) the Benoist's anisotropic diffusion coefficients. The significantly large discrepancy previously reported was reduced down to about 1 % Dk/k by the revised annular core model.

Journal Articles

Benchmark analyses of neutron streaming experiments for proton accelerator facilities

Nakano, Hideo*; Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo*; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*

Journal of Nuclear Science and Technology, 41(Suppl.4), p.50 - 53, 2004/03

In order to estimate accuracy of the various calculation methods for the neutron streaming through a maze and duct in proton accelerator facilities, we performed benchmark analyses by using the radiation shielding design codes. According to the results of the benchmark analyses, it is concluded that NMTC/MCNP, MCNPX and DUCT-III are applicable to actual calculation of the duct-streaming radiations for J-PARC.

JAEA Reports

Verification of the DUCT-III for calculation of high energy neutron streaming

Masukawa, Fumihiro; Nakano, Hideo*; Nakashima, Hiroshi; Sasamoto, Nobuo; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*; Hirayama, Hideo*; Shin, Kazuo*

JAERI-Tech 2003-018, 42 Pages, 2003/03


no abstracts in English

JAEA Reports

$$gamma$$-ray spectra of short half-life nuclides

Kamemoto, Yuichiro; Shiba, Koreyuki; Handa, Nuneo; Okada, Minoru

JAERI 4019, 20 Pages, 1961/10


no abstracts in English

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