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F and comparison of the structure among perovskite-type oxyfluoridesKatsumata, Tetsuhiro*; Suzuki, Ryo*; Sato, Naoto*; Suzuki, Shumpei*; Nakashima, Mamoru*; Inaguma, Yoshiyuki*; Mori, Daisuke*; Aimi, Akihisa*; Yoneda, Yasuhiro
Journal of Solid State Chemistry, 279, p.120919_1 - 120919_8, 2019/11
Times Cited Count：10 Percentile：47.15(Chemistry, Inorganic & Nuclear)
Eu M
ssbauer spectroscopyHomma, Yoshiya*; Kakihana, Masashi*; Tokunaga, Yo; Yogi, Mamoru*; Nakashima, Miho*; Nakamura, Ai*; Shimizu, Yusei*; Li, D.*; Maurya, A.*; Sato, Yoshiki*; et al.
Journal of the Physical Society of Japan, 88(9), p.094702_1 - 094702_8, 2019/08
Times Cited Count：9 Percentile：58.97(Physics, Multidisciplinary)Yoshikawa, Hideki; Kawakita, Masakazu*; Fujiwara, Kazuhiro*; Sato, Tomofumi; Asano, Takahiro*; Sasaki, Yoshito
Materials Research Society Symposium Proceedings, Vol.1475, p.617 - 622, 2012/06
Since it was suggested that the microbes have ability to generate their biofilm in deep underground condition, we examined the effects of biofilm on radionuclide migration scenario. To estimate the effect on matrix diffusion, through diffusion experiment for a biofilm of Desulfovivrio desullfuricans were performed. The effective diffusion coefficient of the biofilm was 10
m
/s order which was about ten times smaller than that in free water. It is suggesting that the microbes and biofilm will not interfere with matrix diffusion as a retardation of radionuclide in rock.
Uozumi, Yusuke*; Iwamoto, Hiroki*; Koba, Yusuke*; Matsufuji, Naruhiro*; Sanami, Toshiya*; Satoh, Daiki; Shigyo, Nobuhiro*; Takada, Masashi*; Ueyama, Masahiko*; Yoshioka, Masakatsu*; et al.
Progress in Nuclear Science and Technology (Internet), 1, p.114 - 117, 2011/02
It is important to assess and suppress the potential for second cancer induction by secondary neutrons produced in primary heavy-ion fragmentation in patient body. Since it is very difficult to measure high-energy neutron doses in mixed radiation fields, a Monte-Carlo simulation approach has attracted much attention as an alternative for neutron dose estimation. It is notoriously hard to reproduce the spectral cross sections of neutrons from high-energy heavy-ion collisions. We, therefore, have planned experiments to measure energy-angle double-differential cross sections of nuclear reactions.
Iwamoto, Yosuke; Taniguchi, Shingo*; Nakao, Noriaki*; Itoga, Toshio*; Nakamura, Takashi*; Nakane, Yoshihiro; Nakashima, Hiroshi; Satoh, Daiki; Yashima, Hiroshi*; Yamakawa, Hiroshi*; et al.
Nuclear Instruments and Methods in Physics Research A, 562(2), p.789 - 792, 2006/06
Times Cited Count：6 Percentile：43.77(Instruments & Instrumentation)Neutron energy spectra produced from thick targets play an important role in validation of calculation codes that are employed in the design of spallation neutron sources and the shielding design of accelerator facilities. However, appropriate experimental data were scarce in the forward direction for the incident energy higher than 100 MeV. In this study, neutron spectra at 0 degree from thick targets bombarded with 350 MeV protons were measured by the time-of-flight technique using an NE213. The targets used were graphite, Al, Fe and Pb and their thicknesses were chosen to be a little thicker than the stopping lengths. The experiment was carried out at the TOF course of the RCNP (Research Center of Nuclear Physics) ring cyclotron, Osaka University. The flight path length between center of the target and of an NE213 were 11.4 m for the measurement of low energy neutrons and 95 m for high energy neutrons. The experimental data are compared with the calculated results by using the Monte Carlo transport codes, such as MCNPX and PHITS codes.
*; *; *; *; Matsuzuru, Hideo
JAERI-M 89-200, 26 Pages, 1989/12
no abstracts in English
Cs and 
Sr from Simulated High-Level Waste Glass; ; *; ; ;
JAERI-M 84-141, 17 Pages, 1984/08
no abstracts in English
*; *; *; *; *; *
PNC TN941 79-173, 109 Pages, 1979/10
The series of the scoping test which ascertains whether the secondary failure of the adjucent heat transfer tube occure or not due to large leak sodium water reaction in steam generator of LMFBR is beeing performed using SWAT-3 test facility. This paper describes the post-test inspection result of the reaction vessel internal with downcommer heat transfer tube bundles which was used in Run-7 test. The internal was designed and manufactured by TOSHIBA/IHI based on their design of the MONJU's steam generator. Run-7 test was excecuted with the water injection point of the middle part of the tube bundle, and water injection rate and duration of 10.6 (initial) to 7.9 kg/sec (afterward) and 9.5 seconds. Total quantity injected water was 85 kg. No secondary tube failure and blister due to the high temperature and tube wall softening caused by high temperature generated by sodium water reaction was obserbed. Some bowing were obserbed on the heat transfer tube, and some damage were obserbed on the sensor cables and it's banding wire closed to water injection point.
*; *; *; *; *; *
PNC TN941 79-172, 63 Pages, 1979/10
The series of the scoping test which ascertains whether the secondary failure of the adjucent heat transfer tube occure or not due to large leak sodium water reaction in steam generator of LMFBR is beeing performed using SWAT-3 test facility. This paper describes the post-test inspection result of the reaction vessel internal with helically coiled heat transfer tube bundles which was used in run-6 sodium water reaction test. The internal was manufactured by HITACHI/BHK company based on their design of the MONJU's SG. Run-6 test was excecuted with the water injection point of the lower part of the tube bundle, and water injection rate and duration of 9.4 (initial) to 8.3 kg/sec (afterward) and 9.5 seconds. Total weight of injected water was 90 kg. No secondary tube failure occure during and after sodium water reaction. No deformations of heat transfer tube which include the deformation due to mechanical force and blister due to the high internal pressure and tube wall softening caused by high temperature generated by sodium water reaction was obserbed. Some deformations were obserbed on the shroud of internal.
*; *; *; *; *; *
PNC TN941 79-167, 66 Pages, 1979/09
The series of the scoping test which ascertains whether the secondary failure of the adjucent heat transfer tube occure or not due to large leak sodium water reaction in steam generator of LMFBR is beeing performed using SWAT-3 test facility. This paper describes the post-test inspection result of the reaction vessel internal with helically coiled heat transfer tube bundles which was used in run-5 sodium water reaction test. The internal was manufactured by TOSHIBA/IHI company based on their design of the MONJU's SG. Run-5 test was excecuted with the water injection point of the lower part of the tube bundle, and water injection rate and duration of 15 (initial) to 11 kg/sec (afterward) and 9.7 seconds. Total weight of injected water was 150 kg. No secondary tube failure, deformation of heat transfer tube which include the deformation due to mechanical force and blister due to the high internal pressure and tube wall softening caused by high temperature generated by sodium water reaction were observed. Some deformations were obserbed on the hanger bolts and the shroud of internal.
*; *; *; *; *; *
PNC TN941 79-166, 53 Pages, 1979/09
The series of the scoping test which ascertains whether the secondary failure of the adjucent heat transfer tube occure or not due to large leak sodium water reaction in steam generator of LMFBR is beeing performed using SWAT-3 test facility. This paper describes the post-test inspection result of the reaction vessel internal with helically coiled heat transfer tube bundles which was used in run-4 sodium-water reaction test. The internal was manufactured by TOSHIBA/IHI company based on their design of the MONJU's SG. Run-4 test was excecuted with the water injection point of the upper part of the tube bundle, and water injection rate and duration of 9.0 (initial) to 7.2 kg/sec (afterward) and 9.4 seconds. Total weight of injected water was 83.0 kg. No secondary tube failure and blister due to high internal pressure and wall softening caused by high temperature generated by sodium water reaction was obserbed. A little deformation was obserbed on the shroud.
*; *; *; *; *
PNC TN941 79-165, 57 Pages, 1979/09
The series of the scoping test which ascertains whether the secondary failure of adjucent heat transfer tube occure or not due to large leak sodium water reaction in steam generator of LMFBR is beeing performed using SWAT-3 test facility. This paper describes the post-test inspection result of the reaction vessel internal with helically coiled heat transfer tube bundles which was used in run-3 sodium-water reaction test. The internal was manufactured by TOSHIBA/IHI company based on their design of the MONJU's SG. Run-3 test was excecuted with the water injection point of the lower part of the tube bundle, and water injection rate and duration of 8.8 (initial) to 7.9 kg/sec (afterward) and 9.5 seconds. Total weight of injected water was 78.0 kg. No secondary tube failure and the blister due to high internal pressure and tube wall softening caused by high temperature generated by sodium-water reaction was observed. Some deformations were obserbed on a few heat transfer tubes, a shroud, and a sensor tube of the sodium level meter.
*; *; *; *; *; *
PNC TN941 79-152, 52 Pages, 1979/09
The series of the scoping test which ascertains whether the secondary failure of the adjucent heat transfer tube occure or not by large leak sodium water reaction in steam generator of LMFBR is being performed using SWAT-3 test facility. This paper describes the post-test inspection result of the reaction vessel internal with helically coiled hart transfer tube bundles which was used in Run-2 sodium-water reaction test. The internal was munufuctured by Toshiba/IHI company based on their design of the MONJU's SG. Run-2 test was excecuted with the water injection point of the lower part of the tube bundle, and water injection rate and duration of 14.2 (initial) to 9.7 Kg/sec (afterward) and 9.9 seconds. The result is summarized as follows; (1)No secondary tube failure occure during and after sodium water reaction. (2)No deformations of heat transfer tube which include the deformation due to mechanical force and the blister due to the high internal pressure and tube wall softening caused by high temperature generated by sodium-water reaction was obserbed. (3)A little trace (polishing) of the wastage phenomena was obserbed on the adjucent tube walls of water injection point. (4)Some deformations were obserbed on a hanger bolt of the internal and a seneor tube of the sodium level meter.
*; *; *; *; *; *; *
PNC TN941 78-46, 23 Pages, 1978/01
In the large leak sodium-water reaction experiment for safe design of LMFBR's steam generator, following two troubles were found with the burst detector (metal-ribon cutting type) of rupture disk which was settled in the pressure relief-line of the large scale sodium-water reaction test facility SWAT-3. (1)Missing the signal detection of rupture disk bursted owing to slow action of the burst-detecting circuit with the electric relay. (2)Leaking of sodium through the electrodes of the metal-ribbon which penetrated the piping wall of pressure relief line. In order to improve the troubled parts, the replacement of the semi-conductor circuit including simple logical circuit instead of the relay device of the detector and the change of the electrode's structure were performed. It was confirmed in the following experiment that improvements were accomplished.
*; Hiroi, Hiroshi*; *; *; *; *
PNC TN941 76-38, 82 Pages, 1976/04
Part of SWAT-1 facility was modified and relief system performance tests have been conducted in the period, June 1974 to March 1975. A series of seven large leak sodium-water reaction experiments have been performed and the test results have been analyzed by computer codes. A brief summary of the test results and analysis is as follows: (1)Many unclear problems associated with the wave-guide-type pressure measurements obtained earlier have been clarified. (2)Test results provided the relationship between the realized initial spike pressure with leak rate (water injection rate), the sonic speed measurements, and the relationship between the initial spike pressure with the strain measurments on the vessel wall. (3)Measurements were made of pressure, temperature, the amount of sodium transfer and the initial sodium velocity in the relief line, and etc. for various leak rate and two types of relief system configuration (top-and side-mounted systems). (4)The comparison of the SWAC-9A and SWAC-109 code calculations revealed that the SWAC-109 result agreed more closely with the test results than the SWAC-9A.
*; *; *; *; *; *
PNC TN941 72-02, 66 Pages, 1972/02
The PNC's large-leak sodium-water reaction test was started in Dec. 1970 using SWAT-1 test rig. In this paper, the results of series I test are described. The experimetal results of the six tests are presented, and the pressure build-up in reaction vessel and cyclone separator, and the heat balance of reaction energy are diseussed.
Endo, Akira; Sato, Tatsuhiko; Satoh, Daiki; Shikaze, Yoshiaki; Tanimura, Yoshihiko; Saegusa, Jun; Tsutsumi, Masahiro; Yamaguchi, Yasuhiro; Kaneko, Hirohisa; Oda, Keiji*; et al.
no journal, ,
no abstracts in English
