Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Yamamoto, Masahiko; Nishida, Naoki; Kobayashi, Daisuke; Nemoto, Ryo*; Hayashi, Hiroyuki*; Kitao, Takahiko; Kuno, Takehiko
JAEA-Technology 2023-004, 30 Pages, 2023/06
JAEA-Technology-2023-004.pdf:1.94MB
Glove-box gloves, that are used for handling nuclear fuel materials at the Tokai Reprocessing Plant (TRP) of the Japan Atomic Energy Agency, have an expiration date by internal rules. All gloves are replaced at a maximum of every 4-year. However, degrees of glove deterioration varies depending on its usage environment such as frequency, chemicals, and radiation dose. Therefore, physical properties such as tensile strength, elongation, hardness of gloves are measured and technical evaluation method for the glove life-time is established. It was found that gloves without any defects in its appearance have enough physical properties and satisfies the acceptance criteria values of new gloves. Thus, it was considered that the expired gloves could be used for total of 8-year, by adding 4-year of new glove life-time. In addition, the results of extrapolation by plotting the glove's physical properties versus the used years showed that the physical properties at 8-year is on the safer side than the reported physical properties of broken glove. Also, the data are not significantly different from the physical properties of the long-term storage glove (8 and 23 years). Based on these results, life-time of gloves at TRP is set to be 8-year. The frequency of glove inspections are not changed, and if any defects is found, the glove is promptly replaced. Thus, the risk related to glove usage is not increased. The cost of purchasing gloves, labor for glove replacement, and the amount of generated waste can be reduced by approximately 40%, respectively, resulting in more efficient and rationalized glove management.
Akino, Norio
Nihon Kikai Gakkai Ryutai Kogaku Bumon Koenkai Koen Gaiyoshu (CD-ROM), 4 Pages, 2001/10
no abstracts in English
Takeda, Seietsu; ; ; Nakatsuka, Noboru; Nakano, Katsushi; ; Ishimaru, Tsunenori
JNC TN7410 2000-003, 65 Pages, 2000/11
*; *; Yabuuchi, Satoshi
JNC TY7400 2000-001, 72 Pages, 2000/03
JNC-TY7400-2000-001.pdf:4.01MB
None
Harada, Katsuya; Nishino, Yasuharu; Mita, Naoaki; Amano, Hidetoshi
JAERI-Tech 2000-031, p.27 - 0, 2000/03
JAERI-Tech-2000-031.pdf:2.95MB
no abstracts in English
*; *
JNC TJ7400 2000-001, 79 Pages, 2000/02
JNC-TJ7400-2000-001.pdf:3.07MB
no abstracts in English
Sato, Takeshi; Tamaki, Hitoshi
JAERI-Data/Code 2000-009, p.120 - 0, 2000/02
JAERI-Data-Code-2000-009.pdf:5.06MB
no abstracts in English
Kinoshita, Hidetaka; Kaminaga, Masanori; Hino, Ryutaro
JAERI-Tech 99-017, 34 Pages, 1999/03
no abstracts in English
Nakanishi, Koki*; Arai, Taketoshi; Burchell, T. D.*
Extende Abstracts, International Symposium on Carbon, Science and Technology for New Carbons, p.332 - 333, 1998/00
no abstracts in English
Hino, Ryutaro; Haga, Katsuhiro; ; ; *; Kaminaga, Masanori; Sudo, Yukio; *
JAERI-Tech 97-009, 50 Pages, 1997/03
no abstracts in English
Takeda, Tetsuaki; B.Han*; Ogawa, Masuro
JAERI-M 92-131, 125 Pages, 1992/09
no abstracts in English
; H.Cords*; H.Nickel*
Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.553 - 558, 1991/00
no abstracts in English
Ogawa, Masuro
JAERI 1318, 44 Pages, 1989/07
no abstracts in English
Asahi, Yoshiro; *
JAERI-M 86-088, 46 Pages, 1986/06
no abstracts in English
; Akino, Norio; *
JAERI-M 83-018, 17 Pages, 1983/02
no abstracts in English
Sudo, Yukio
Journal of Nuclear Science and Technology, 17(1), p.1 - 15, 1980/00
Times Cited Count：15 Percentile：80.15(Nuclear Science & Technology)no abstracts in English
Ogawa, Masuro; Takizuka, Takakazu; Sanokawa, Konomo
JAERI-M 8466, 32 Pages, 1979/10
no abstracts in English
Ogawa, Masuro; Takizuka, Takakazu; Sanokawa, Konomo
JAERI-M 8109, 35 Pages, 1979/02
no abstracts in English
Higashi, Hideo*; Fukuyama, Hiroyuki*; Nishi, Tsuyoshi*; Yamano, Hidemasa
no journal, ,
Thermophysical properties of molten stainless steel (SUS316) are necessary to understand a core degradation mechanism in severe accidents of nuclear reactors. In this study, the normal spectral emissivity, heat capacity and thermal conductivity of liquid SUS316 were measured using an electromagnetic levitation technique in a dc magnetic field. The normal spectral emissivity has a negative wavelength dependence, and a negligible temperature dependence. The heat capacity and thermal conductivity of liquid SUS316 were measured using the noncontact laser modulation calorimetry. The heat capacity presents a constant value at a temperature range from 1661 to 1778 K. The thermal conductivity has a positive temperature dependence.
