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JAEA Reports

The calculation and estimation of wastes generated by decommissioning of nuclear facilities

; ; ; Takeda, Seiichiro

JNC TN8420 2001-008, 134 Pages, 2001/07

JNC-TN8420-2001-008.pdf:4.4MB

This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decomissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decomissioning of the nuclear facilities are as follows. (1)Tokai works. The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2)Ningyo-toge Environmental Engineering Center. The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton.

JAEA Reports

Long-term effect of creep displacement of host-rock on stability of engineered barrier system for TRU waste; Two-dimensional analysis by the non-linear viscoelasticity model

Aoyagi, Takayoshi*; *; Mihara, Morihiro; Okutsu, Kazuo*; Maeda, Munehiro*

JNC TN8400 2001-024, 103 Pages, 2001/06

JNC-TN8400-2001-024.pdf:8.84MB

In the disposal concept of TRU waste, concentrated disposal of wastes forms in large cross-section underground cavities is envisaged, because most of TRU waste is no-heat producing in spite of large generated volume as compared with HLW. In the design of engineered barrier system based on large cross-section cavities, it is necessary to consider the long-term mechanical process such as creep displacement of the host rock from the viewpoint of the stability of engineered barrier system. In this study, the long-term creep displacement of the host rock was calculated using the non-linear viscoelasticity model and the effects on the stability of engineered barrier system was evaluated. As a result, in the disposal concept of crystalline rock, no creep displacement occurred at the time after 1 milion year. On the other hand, in the disposal concept of sedimentary rock, creep displacement of 80$$sim$$90mm occurred at the time after 1 milion year. Also, in this calculation, a maximum reduction of 45mm concerned with the thickness of buffer material was estimated. But these values resulted within allowance of design values. Therefore, these results show that the effects of the creep displacement on the stability of engieered barrier system would not be significant.

Journal Articles

Beam performance of negative-ion based NBI system for JT-60

Ito, Takao; Akino, Noboru; Ebisawa, Noboru; Grisham, L. R.*; Honda, Atsushi; Hu, L.*; Kawai, Mikito; Kazawa, Minoru; Kuriyama, Masaaki; Kusaka, Makoto*; et al.

Fusion Engineering and Design, 51-52, p.1039 - 1047, 2000/11

 Times Cited Count:15 Percentile:68.6(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A Basic study on electrolytic decomposition of butylamine; A Study on decomposition of butylamine solvent washing reagent

Kamei, Kazushige; Hotoku, Shinobu; Asakura, Toshihide; Watanabe, Makio; Uchiyama, Gunzo; Fujine, Sachio

JAERI-Research 2000-021, p.29 - 0, 2000/03

JAERI-Research-2000-021.pdf:1.37MB

no abstracts in English

JAEA Reports

None

Tanimoto, Kenichi

PNC TN9450 98-002, 52 Pages, 1998/01

PNC-TN9450-98-002.pdf:11.7MB

None

JAEA Reports

None

Wada, Ryutaro*; Nishimura, Tsutomu*; Fujiwara, Kazuo*; *; *

PNC TJ1058 97-003, 33 Pages, 1997/03

PNC-TJ1058-97-003.pdf:2.63MB

None

Journal Articles

Evaluation of value for hydrogen release from high-level liquid waste, 4; Hydrogen release rate for $$gamma$$-ray radiolysis of simulated purex waste solutions

Miyata, Teijiro; Nakagiri, Naotaka*

Nihon Genshiryoku Gakkai-Shi, 39(12), p.1062 - 1068, 1997/00

 Times Cited Count:4 Percentile:37.09(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of value for hydrogen release from high-level liquid waste,III; Influence of metal components on hydrogen release from gamma-ray irradiated aqueous nitric acid solution

; Miyata, Teijiro

Nihon Genshiryoku Gakkai-Shi, 38(12), p.992 - 1000, 1996/00

 Times Cited Count:1 Percentile:14.44(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Study on life estimation of cable insulation by gas evolution and oxygen consumption during radiation and thermal aging

*; *; *; Yagi, Toshiaki; Seguchi, Tadao

Mitsubishi Densen Kogyo Jiho, (87), p.45 - 49, 1994/04

no abstracts in English

JAEA Reports

Initial results from neutron yield measurements by activation technique at JT-60U

M.Hoek*; Nishitani, Takeo; Ikeda, Yujiro; Morioka, Atsuhiko

JAERI-M 94-002, 25 Pages, 1994/01

JAERI-M-94-002.pdf:0.92MB

no abstracts in English

JAEA Reports

None

*

PNC TN9080 93-002, 26 Pages, 1992/12

PNC-TN9080-93-002.pdf:1.0MB

None

JAEA Reports

None

Nakano, Tomoyuki;

PNC TN9420 92-008, 119 Pages, 1992/06

PNC-TN9420-92-008.pdf:3.71MB

None

JAEA Reports

None

; *; *; ; ; Enokido, Yuji

PNC TN9080 92-004, 55 Pages, 1992/03

PNC-TN9080-92-004.pdf:1.38MB

None

Journal Articles

Gamma-ray irradiation effects on cubic silicon carbide metal-oxide-semiconductor structure

Yoshikawa, Masahito; Morita, Yosuke; Ito, Hisayoshi; Nashiyama, Isamu*; *; Okumura, Hajime*; Yoshida, Sadafumi*

Amorphous and Crystalline Silicon Carbide IV, p.393 - 398, 1992/00

no abstracts in English

Journal Articles

Effects of gamma-ray irradiation on cubic silicon carbide metal-oxide-semiconductor structure

Yoshikawa, Masahito; Ito, Hisayoshi; Morita, Yosuke; Nashiyama, Isamu*; *; Okumura, Hajime*; Yoshida, Sadafumi*

Journal of Applied Physics, 70(3), p.1309 - 1312, 1991/08

 Times Cited Count:38 Percentile:85.1(Physics, Applied)

no abstracts in English

JAEA Reports

Journal Articles

Characteristics of fusion reaction rate and neutron yield in deuterium plasma

Niikura, Setsuo; Nagami, Masayuki; Horiike, Hiroshi

Fusion Engineering and Design, 6, p.181 - 191, 1988/00

 Times Cited Count:6 Percentile:57.08(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Decommissioning of Tokai Reprocessing Plant (TRP), 3; Evaluation of waste generation and decommissioning cost

Hashimoto, Kowa; Okano, Masanori; Taguchi, Katsuya; Nagasato, Yoshihiko

no journal, , 

The Tokai Reprocessing Plant has many facilities, various installation and complicated systems, which are contaminated by radioactive materials. Based on this feature, JAEA estimated its waste generation and the cost for decommissioning by using common and reasonable condition for many and complicated facilities.

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