Skyshine dose evaluation of trench disposal facilities for waste generated from research, industrial and medical facilities

Nakamura, Mizuki; Izumo, Sari; Ogawa, Rina; Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro

JAEA-Technology 2022-025, 73 Pages, 2022/12

JAEA-Technology-2022-025.pdf:1.64MB

Japan Atomic Energy Agency (JAEA) has been establishing as the implementing body of the near surface disposal of low-level radioactive waste (LLW) generated from research facilities and other facilities in order to actualize the near surface disposal. It is necessary to evaluate the effective doses by direct and skyshine -rays from disposal facilities and reduce the doses below the target dose (50 Sv/y) at the site boundary for the safety assessment during operation. It was shown at the results of conceptual design that the distance from the trench disposal facilities to site boundary needed to be kept more than 120m in order to satisfy the target dose. However, the design of trench disposal facilities was changed because of increasing amount of waste subject to the trench disposal. Therefore, the dose by skyshine -rays from trench disposal facilities was recalculated by use of two-dimensional discrete ordinates Sn code DOT 3.5. As a result, it was evaluated that the dose by skyshine -rays from each trench facility at the site boundary whose distance was 120m from a trench facility was lower than 50 Sv/y, respectively, and the dose added up the doses from trench facilities was also lower than 50 Sv/y. In addition, it was suggested to reduce the target skyshine dose by thickening the covered soil on the top layer.

Revise of a basic data base for shielding design

*; Takemura, Morio*

JNC TJ9440 2000-005, 157 Pages, 2000/03

JNC-TJ9440-2000-005.pdf:3.7MB

With use of the two-dimensional discrete ordinates code DORT and the standard groupwise shielding design library JSSTDL produced from the latest evaluated nuclear data library JENDL-3.2, experimental analyses for the representative configurations in the Radial Shield Attenuation Experiment of the JASPER were performed. The results were compared with those obtained with use of traditional method DOT3.5/JSDJ2 for the previous JASPER experimetal analyses. In general, the change of the cross section library gives higher results and the change of the transport code gives lower results. Finally the new analysis method gives better agreement with the experimental results and also less deviations of calculational errors between various detectors. Experimental analyses for the thick concrete configulation in the Gap Streaming Experiment of the JASPER was also performed with the new analysis method, after solving the poor agreement found in last year with the original JASPER experimental analyses. The same tendency due to the library change was confirmed with the above mentioned analyses of the Radial Shield Attenuation Experiment. Compilation of the input data necessary for future reanalyses of important configurations in JASPER experiments were continued through the above-mentioned experimental analyses and related informations were added for repletion of the database preserved in a computer disk holding previously accumulated data. Input data descriptions were made for auxiliary routines needed for the experimental analyses and their sample data were compiled and stored in the database.

Shielding analysis of neutron detector guide tubes of advanced marine reactor MRX

*; Ishida, Toshihisa; *

JAERI-Tech 98-030, 38 Pages, 1998/08

JAERI-Tech-98-030.pdf:1.73MB

no abstracts in English

Benchmark experiment on bulk shield of SS316/water with simulated superconducting magnet

Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Wada, Masayuki*; Ikeda, Yujiro; Maekawa, Hiroshi; Kasugai, Yoshimi; M.Z.Youssef*; A.Kumar*; M.A.Abdou*

Fusion Engineering and Design, 42, p.267 - 273, 1998/00

https://doi.org/10.1016/S0920-3796(97)00188-9

no abstracts in English

Transmission through shields of quasi-monoenergetic neutrons generated by 43- and 68-MeV protons,II; Iron shielding experiment and analysis for investigating calculational method and cross-section data

; Nakao, Noriaki*; Tanaka, Shunichi; Nakamura, Takashi*; Shin, Kazuo*; Tanaka, Susumu; Takada, Hiroshi; Meigo, Shinichiro; Nakane, Yoshihiro; Sakamoto, Yukio; et al.

Nuclear Science and Engineering, 124(2), p.243 - 257, 1996/00

https://doi.org/10.13182/NSE96-A28575

no abstracts in English

Benchmark experiment on copper with D-T neutrons for verification of neutron transport and related nuclear data of JENDL-3.1

Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro; Maekawa, Hiroshi

Fusion Engineering and Design, 28, p.745 - 752, 1995/00

no abstracts in English

Pre-evaluation of fusion shielding benchmark experiment

*; *; Konno, Chikara; Maekawa, Fujio; Maekawa, Hiroshi; *; *; *

Fusion Engineering and Design, 28, p.525 - 533, 1995/00

https://doi.org/10.1016/0920-3796(94)00236-Z

no abstracts in English

Pre-analyses of SS316 and SS316/Water bulk shielding experiments

Konno, Chikara; Maekawa, Fujio; *; Kosako, Kazuaki*; Ikeda, Yujiro; Oyama, Yukio; Maekawa, Hiroshi

JAERI-Tech 94-019, 43 Pages, 1994/10

JAERI-Tech-94-019.pdf:1.64MB

no abstracts in English

Shielding experiments with quasi-monoenergetic neutrons between 15 and 90 MeV at 90 MV AVF cyclotron facility TIARA

Sakamoto, Yukio; ; Nakane, Yoshihiro; Tanaka, Shunichi; Tanaka, Susumu; Nakamura, Takashi*; Baba, Mamoru*; *; Shin, Kazuo*

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.809 - 815, 1994/00

no abstracts in English

Evaluation of skyshine dose rate due to gamma-rays from activated cooling water in fusion experimental reactors

Sato, Satoshi; *; Seki, Yasushi; Takatsu, Hideyuki; Mori, Seiji*

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.946 - 953, 1994/00

no abstracts in English