Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Saito, Shigeru; Yamaguchi, Kazushi*; Yoshimoto, Hidemitsu*; Obayashi, Hironari; Sasa, Toshinobu
JAEA-Technology 2022-032, 51 Pages, 2023/03
JAEA-Technology-2022-032.pdf:4.51MB
In the Accelerator Driven System (ADS) being studied by the Japan Atomic Energy Agency (JAEA) for transmutation of long-lived radioactive waste, lead-bismuth eutectic alloy (LBE) is used as a spallation target and subcritical core coolant. A proton irradiation facility in J-PARC is considered to prepare a material irradiation database for ADS development. The proton irradiation facility is equipped with an LBE loop, which enables material irradiation tests in spallation environment under flowing LBE condition. The slow leakage of LBE is one of critical issue to use LBE safety. The slow leakage is caused by the biting slag and/or other materials at valve seal of drain valve. To solve this problem, JAEA examined the application of freeze-seal valve (FSV), which seal the piping by freezing LBE in specific position. Water-cooled and air-cooled freeze-seal valve test modules were fabricated, installed in the test section of the existing test stand for LBE technology development, and tested to confirm their operation and performance. As a result of the tests, it was confirmed that the water-cooled FSV test module worked well along to the design values. This report describes the outline and details of the test stand for LBE technology and each FSV test module, as well as the results of operation and performance verification tests.
Antariksawan, A. R.*; Hidaka, Akihide; Moriyama, Kiyofumi; Hashimoto, Kazuichiro*
JAERI-Tech 2001-011, 116 Pages, 2001/03
JAERI-Tech-2001-011.pdf:4.02MB
no abstracts in English
Ogawa, Toshihide; Saigusa, Mikio*; Kawashima, Hisato; Kanazawa, Sadayoshi*; JFT-2M Group
Fusion Technology, 39(1T), p.305 - 308, 2001/01
no abstracts in English
Raman, R.*; Itami, Kiyoshi
Purazuma, Kaku Yugo Gakkai-Shi, 76(10), p.1079 - 1087, 2000/10
no abstracts in English
Fujita, Reiko*; *; Kondo, Naruhito*; Utsunomiya, Kazuhiro*
JNC TJ8420 2000-004, 41 Pages, 2000/03
JNC-TJ8420-2000-004.pdf:5.08MB
no abstracts in English
; *; Tokizawa, Takayuki; *
JNC TY6400 2000-013, 102 Pages, 2000/02
JNC-TY6400-2000-013.pdf:2.45MB
None
Aoyagi, Takayoshi*; Mihara, Morihiro; Tanaka, M.*; Okutsu, Kazuo*
JNC TN8400 99-058, 55 Pages, 1999/11
For the emplaced waste in TRU waste disposal facility, it may have the void for waste bodies it. And, generating void which accompanies those component elution in concrete pit and filler in which the cement material becomes the candidate material is assumed. It is considered that the security of the diffusion control in the bentonite is not done when these voids collapsed, and when it generated the volume change inside the buffer material (bentonite). The imperfect blockage of the void by not obtaining, the sufficient swelling pameability swelling bentonite is a cause on this. Then, volume change of the bentonite inside is analyzed in this study under the conservative estimation. And the following are tested: Self-sealing, maximum swelling rate, density distribution change of the batonite. Evaluation of the engineered barrier system for volume change from the result was carried out. Prior to the evaluation, generating void was calculated based on the conservative estimation. The density of the buffer material as it assumed the blocking by buffer material uniformly awelling using this calculated data, was obtained. By the permeability got from existing research result which shows the relationship between density and permeability of the bentonite, it was confirmed to become diffusion control in the buffer material inside, in existing engineered barrier specification. Next, it was tested, when the conservative void of the superscription was assumed, in order to confirm whether it does the security, as permeability necessaly for maintaining diffusion control, puts it for the swelling of actual bentonite. As the result, it was possible to confirm sufficient swelling performance in order to do the security of the diffusion control in Na-bentonite. However, the swelling performance greatly lowered by comparing Na-bentonite in Ca-bentonite with under 1/6. The increase of the permeability not do the security of the diffusion control, when it was based on void quantity ...
Takachi, Kazuhiko; Suzuki, Hideaki*
JNC TN8400 99-041, 76 Pages, 1999/11
The buffer material is expected to maintain its low water permeability, self-sealing properties, radionuclides adsorption and retardation properties, thermal conductivity, chemical buffering properties, overpack supporting properties, stress buffering properties, etc. over a long period of time. Natural clay is mentioned as a material that can relatively satisfy above. Among the kinds of natural clay, bentonite when compacted is superior because (1)it has exceptionally low water permeability and properties to control the movement of water in buffer, (2)it fills void spaces in the buffer and fractures in the host rock as it swells upon water uptake, (3)it has the ability to exchange cations and to adsorb cationic radioelements. In order to confirm these functions for the purpose of safety assessment, it is necessary to evaluate buffer properties through laboratory tests and engineering-scale tests, and to make assessments based on the ranges in the data obtained. This report describes the procedures, test conditions, results and examinations on the buffer material of unconfined compression tests, one-dimensional consolidation tests, consolidated-undrained triaxial compression tests and consolidated-undrained triaxial creep tests that aim at getting hold of static mechanical properties. We can get hold of the relationship between the dry density and tensile stress etc. by Brazillian tests, between the dry density and unconfined compressive strength etc. by unconfined compression tests, between the consolidation stress and void ratio etc. by one-dimensional consolidation tests, the stress pass of each effective confining pressure etc. by consolidated-undrained triaxial compression tests and the axial strain rate with time of each axial stress etc. by consolidated-undrained triaxial creep tests.
Taguchi, Ko*; Tada, Eisuke
JAERI-Tech 99-079, p.28 - 0, 1999/11
no abstracts in English
; ; Kameyama, Iwao; ; ; *; *
JAERI-Tech 99-075, p.87 - 0, 1999/10
no abstracts in English
Abe, Hiroshi; ; *; *; *; *; Kaneta, Takayoshi*; *; Suzuki, Hiromitsu; Tani, Norio; et al.
JAERI-Research 97-068, 51 Pages, 1997/10
JAERI-Research-97-068.pdf:1.78MB
no abstracts in English
Ito, Hideaki; ; ; Okubo, Toshiyuki
PNC TN9410 96-298, 177 Pages, 1996/11
The fuel handling facility in "JOYO" must maintain an argon atmosphere and be gas tight; this prevents the oxidation of sodium adhering to a fuel assembly and leakage of radioactive gases. Periodic leak testing of the double O-ring gas seal had been performed at increasing pressure to assure its specified leak tightness. The problem with this method was that it took a long time to obtain an accurate measurement. The leak testing methods for the fuel handling facility, the reactor containment vessel, and other vessels were all reexamined. As a consequence, it was determined that alternative devices and methods for improving the leak rate measurements should be studied. Four methods of leak testing were evaluated; the present increasing pressure method, helium leak testing, decreasing pressure method, and a liquid nitrogen decreasing pressure method. A new automatic leak measurement device was used in these evaluations. The results of the utilization and limitations of the four methods of leak testing are summarized as follows. (1) The decreasing pressure leak testing method was efficient with regard to accuracy and stability for use in the fuel handling facility. (2) The automatic leak measurement device used a statistical calculation to measure the leak rate stability and it met the specified measurement requirements. (3) The leak rate measuring time was reduced by half with this new device and it could also simultaneously examine other objects.
Hidaka, Akihide; Ezzidi, A.*; Sugimoto, Jun
PSA 96: Int. Topical Meeting on Probabilistic Safety Assessment, 3, p.1548 - 1556, 1996/00
no abstracts in English
Hayashi, Takumi; Yamada, Masayuki; Konishi, Satoshi; Matsuda, Yuji; Okuno, Kenji; J.E.Nasise*; R.S.Dahlin*; Anderson, J. L.*
Fusion Engineering and Design, 28, p.357 - 361, 1995/00
Times Cited Count：11 Percentile：71.91(Nuclear Science & Technology)no abstracts in English
Shimizu, Katsuhiro; Kubo, Hirotaka; Takizuka, Tomonori; Azumi, Masafumi; Shimada, Michiya; Tsuji, Shunji; Hosogane, Nobuyuki; Sugie, Tatsuo; Sakasai, Akira; Asakura, Nobuyuki; et al.
Journal of Nuclear Materials, 220-222, p.410 - 414, 1995/00
Times Cited Count：51 Percentile：96.73(Materials Science, Multidisciplinary)no abstracts in English
*; *; *; Makuuchi, Keizo; Yoshii, Fumio
Nihon Hoso Gakkai-Shi, 4(2), p.123 - 128, 1995/00
no abstracts in English
Kishimoto, Maki; Sakasai, Kaoru; Ara, Katsuyuki
Simulation and Design of Applied Electromagnetic Systems, p.209 - 212, 1994/00
no abstracts in English
Kishimoto, Maki; Sakasai, Kaoru; Ara, Katsuyuki
MAG-92-235, p.83 - 96, 1992/11
no abstracts in English
; Sasaki, Noriaki; Ishikawa, Hirohisa; Fujita, Tomoo; Sato, Shinji*
PNC TN8410 92-043, 31 Pages, 1992/03
None
Fujii, Tsuneyuki
JAERI-M 92-037, 181 Pages, 1992/03
no abstracts in English
