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Kochiyama, Mami; Okada, Shota; Sakai, Akihiro
JAEA-Technology 2021-010, 61 Pages, 2021/07
JAEA-Technology-2021-010.pdf:3.56MBJAEA-Technology-2021-010(errata).pdf:0.75MB
It is necessary to evaluate the radioactivity inventory in wastes in order to dispose of radioactive wastes generated from dismantling nuclear reactor in the shallow ground. In this report, we examined radioactivity evaluation method for near surface disposal about biological shield concrete near the core generated from the dismantling of JPDR. We calculated radioactive concentration of the target biological concrete using the DORT code and the ORIGEN-S code, and we estimated radioactivity concentration Di (Bq/t). For DORT calculation, the cross-section library created from the MATXSLIB-J40 file from JENDL-4.0 was used, and for ORIGEN-S, the attached library of SCALE6.0 was used. As a result of comparing the calculation results of the radioactivity concentration with the past measured values in the radial direction and the vertical direction, we found that the trends were generally the same. We calculated radioactive concentration of the target biological concrete Di (Bq/t), and we compared with the estimated Ci (Bq/t) equivalent to the dose criteria of trench disposal calculated for 140 nuclides. As a result we inferred that the except for about 2% of target waste could be disposed of in the trench disposal facility. We also preselected important nuclides for trench disposal based on the ratios (Di/Ci) for each nuclide, H-3, C-14, Cl-36, Ca-41, Co-60, Sr-90, Eu-152 and Cs-137 were selected as important nuclides.
Sukegawa, Takenori; Hatakeyama, Mutsuo; Yanagihara, Satoshi
JAERI-Tech 2001-058, 81 Pages, 2001/09
JAERI-Tech-2001-058.pdf:5.98MB
In general, neutron transport and activation calculation codes are used for residual radioactive inventory estimation; however, it is essential to verify calculations by measurement results because of geometrical complexity of the reactor and so on. The comparison between measured and calculated radioactivity in the JPDR core components showed a relatively good agreement (factor of 2), and it was cleared that water content and weight ratio of steel bars to concrete materials significantly influenced the neutron flux distribution in the biological shield (factor of 2-10 error). The measured radioactivity inside of the reactor pressure vessel wall and at the inner part of the biological shield was compared in detail with the calculations to verify the methodology applied to calculations of radioisotope production. Then it was found that the radioactive inventory could be estimated accurately with combination of calculations and measurement of radioactivity in samples and dose rate distribution for planning of dismantling activities.
Sukegawa, Takenori; Hatakeyama, Mutsuo; Yanagihara, Satoshi
Journal of Nuclear Science and Technology, 37(Suppl.1), p.367 - 371, 2000/03
no abstracts in English
Okoshi, Minoru; Yoshimori, Michiro; Abe, Masayoshi
Planning and Operation of Low Level Waste Disposal Facilities IAEA-SM-341/70, 0(0), p.416 - 425, 1997/00
no abstracts in English
Sukegawa, Takenori; ; ; Yanagihara, Satoshi
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 4, 0, p.1779 - 1784, 1995/00
no abstracts in English
Yanagihara, Satoshi; ;
Proc. of the 1993 Int. Conf. on Nuclear Waste Management and Environmental Remediation,Vol. 3, p.423 - 431, 1993/00
no abstracts in English
Hoshi, Tatsuo
IAEA-SR-179, 15 Pages, 1992/00
no abstracts in English
Fujiki, Kazuo; ; ;
Proc. of the Int. Conf. on Dismantling of Nuclear Facilities; Policies-Techniques, p.219 - 232, 1992/00
no abstracts in English
; ; Onodera, Junichi; ; Ikezawa, Yoshio
Proc. of the Int. Conf. on Radiation Effects and Protection, p.434 - 439, 1992/00
no abstracts in English
*; Yanagihara, Satoshi; Sukegawa, Takenori; Tanaka, Mitsugu
Nihon Genshiryoku Gakkai-Shi, 33(6), p.574 - 584, 1991/06
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Hoshi, Tatsuo
Nikkei Konsutorakushon, 0(42), p.24 - 29, 1991/06
no abstracts in English
Onodera, Junichi; ; ; ; Ikezawa, Yoshio
Journal of Aerosol Science, 22(SUPPL.1), p.S747 - S750, 1991/00
no abstracts in English
; Hoshi, Tatsuo; Tachibana, Mitsuo
Low and Intermediate Level Radioactive Waste Management,Vol. 1, p.189 - 195, 1991/00
no abstracts in English
G.Pratapagiri*; Yanagihara, Satoshi; Fujiki, Kazuo; J.Liederman*; Tanaka, Mitsugu
Low and Intermediate Level Radioactive Waste Management,Vol. 1, p.615 - 623, 1991/00
no abstracts in English
Tachibana, Mitsuo; Hoshi, Tatsuo; Miki, Ichiro
Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 2, p.81 - 84, 1991/00
no abstracts in English
;
Nucl. Eng. Int., 0(434), p.35 - 36, 1990/09
no abstracts in English
; Ikezawa, Yoshio
Hoken Butsuri, 25(3), p.294 - 298, 1990/00
no abstracts in English
Yanagihara, Satoshi; ; Nakamura, Hisashi
Nuclear Technology, 86, p.148 - 158, 1989/08
Times Cited Count：12 Percentile：77.45(Nuclear Science & Technology)no abstracts in English
