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JAEA Reports

Study on the evaluation method to determine the radioactivity concentration in radioactive waste generated from the dismantling of research reactors

Murakami, Masashi; Hoshino, Yuzuru; Nakatani, Takayoshi; Sugaya, Toshikatsu; Fukumura, Nobuo*; Sanda, Toshio*; Sakai, Akihiro

JAEA-Technology 2019-003, 50 Pages, 2019/06

JAEA-Technology-2019-003.pdf:4.42MB

Toward the establishment of a common approach to determine the radioactivity concentrations in dismantling wastes arising from research reactors, radionuclide concentrations in the reactor structure materials of aluminum, carbon steel, shield concrete, and graphite of TRIGA Mark II reactor at Rikkyo University, Japan, were evaluated with both radiochemical analysis and theoretical calculation. The measured nuclides by the radiochemical analysis were $$^{3}$$H, $$^{60}$$Co, and $$^{63}$$Ni in aluminum, $$^{3}$$H, $$^{60}$$Co, $$^{63}$$Ni, and $$^{152}$$Eu in carbon steel, $$^{3}$$H, $$^{60}$$Co, and $$^{152}$$Eu in shield concrete, and $$^{3}$$H, $$^{14}$$C, $$^{60}$$Co, $$^{63}$$Ni, and $$^{152}$$Eu in graphite. Neutron-flux distributions and neutron-induced activities were computed with DORT and ORIGEN-ARP codes, respectively. Using the results of material composition analysis, radioactivity concentrations were conservatively predicted with good accuracy except for graphite material.

Journal Articles

Approach for the treatment and disposal of dismantling waste (Research reactor)

Sakamoto, Yoshiaki

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 24(2), p.141 - 146, 2017/12

Some research reactors are under decommissioning or preparation for application of decommissioning license for regulation authority in our country. The reasonable treatment and disposal of dismantling waste is important for decommissioning of research reactors. Therefore, in this paper, JAEA's approach of the treatment and disposal of dismantling waste was introduced from the point of view of disposal of low level radioactive waste arising from research, industrial and medical facilities.

Journal Articles

Cost estimation method for decommissioning of nuclear facilities

Tomii, Hiroyuki; Matsuo, Kiyoshi*; Shiraishi, Kunio; Watabe, Kozo; Saiki, Hideo*; Kawatsuma, Shinji*; Rindo, Hiroshi*; Zaitsu, Tomohisa*

Dekomisshoningu Giho, (31), p.11 - 20, 2005/03

no abstracts in English

JAEA Reports

None

*; *

JNC TJ8420 2000-013, 96 Pages, 2000/03

JNC-TJ8420-2000-013.pdf:6.04MB

no abstracts in English

Journal Articles

Summary and results of the JPDR dismantling project

Miyasaka, Yasuhiko

Dekomisshoningu Giho, 0(14), p.24 - 33, 1996/08

no abstracts in English

Journal Articles

Dismantling of Japan Power Demonstration Reactor (JPDR)

Miyasaka, Yasuhiko

Enerugi Rebyu, 15(9), p.11 - 15, 1995/00

no abstracts in English

JAEA Reports

None

Kawamura, Kazuhiro; ;

PNC TN8600 93-003, 269 Pages, 1993/02

PNC-TN8600-93-003.pdf:8.79MB

no abstracts in English

Journal Articles

Actual management of the JPDR Decommissioning Wastes

Yasunaka, Hideo; ;

Dekomisshoningu Giho, (6), p.50 - 60, 1992/11

no abstracts in English

Journal Articles

Progress of JPDR decommissioning program

; ; Hoshi, Tatsuo; *; ; ; ; ; ; Tachibana, Mitsuo; et al.

Genshiryoku Kogyo, 37(2), p.14 - 59, 1991/02

no abstracts in English

Journal Articles

Treatment,storage and disposal technology for the decommissioned wastes

;

Genshiryoku Kogyo, 29(6), p.34 - 36, 1983/00

no abstracts in English

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