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Sato, Takumi; Otobe, Haruyoshi; Morishita, Kazuki; Marufuji, Takato; Ishikawa, Takashi; Fujishima, Tadatsune; Nakano, Tomoyuki
JAEA-Technology 2023-016, 41 Pages, 2023/09
JAEA-Technology-2023-016.pdf:2.74MB
This report summarizes the results of the stabilization treatments of post-experiment nuclear materials in Plutonium Fuel Research Facility (PFRF) from August 2018 to March 2021. Based on the management standards for nuclear materials enacted after the contamination accident that occurred at PFRF on June 6, 2017, the post-experiment nuclear materials containing plutonium (Pu): samples mixed with organic substances that cause an increase in internal pressure due to radiolysis (including X-ray diffraction samples mixed with epoxy resin and plutonium powder which caused contamination accidents), carbides and nitrides samples which is reactive in air, and chloride samples which may cause corrosion of storage containers, were selected as targets of the stabilization. The samples containing organic materials, carbides and nitrides were heated in an air flow at 650 
C and 950 C for 2 hours respectively to remove organic materials and convert uranium (U) and Pu into oxides. U and Pu chlorides in LiCl-KCl eutectic melt were reduced and extracted into liquid Cd metal by a reaction with lithium (Li) -cadmium (Cd) alloy and converted to U-Pu-Cd alloy at 500 C or higher. All of the samples were stabilized and stored at PFRF. We hope that the contents of this report will be utilized to consider methods for stabilizing post experiment nuclear materials at other nuclear fuel material usage facilities.
Ebihara, Kenichi; Sekine, Daiki*; Sakiyama, Yuji*; Takahashi, Jun*; Takai, Kenichi*; Omura, Tomohiko*
International Journal of Hydrogen Energy, 48(79), p.30949 - 30962, 2023/09
Times Cited Count：0 Percentile：0.01(Chemistry, Physical)To understand hydrogen embrittlement (HE), which is one of the stress corrosion cracking of steel materials, it is necessary to know the H distribution in steel, which can be effectively interpreted by numerical simulation of thermal desorption spectra. In weld metals and TRIP steels, residual austenite significantly influences the spectra, but a clear H distribution is not well known. In this study, an originally coded two-dimensional model was used to numerically simulate the previously reported spectra of high-carbon ferritic-austenitic duplex stainless steels, and it was found that H is mainly trapped at the carbide surface when the amount of H in the steel is low and at the duplex interface when the amount of H is high. It was also found that the thickness dependence of the H desorption peak for the interface trap site is caused by a different reason than the conventional one.
C thin filmNorimatsu, Wataru*; Matsuda, Keita*; Terasawa, Tomoo; Takata, Nao*; Masumori, Atsushi*; Ito, Keita*; Oda, Koji*; Ito, Takahiro*; Endo, Akira*; Funahashi, Ryoji*; et al.
Nanotechnology, 31(14), p.145711_1 - 145711_7, 2020/04
Times Cited Count：6 Percentile：38.95(Nanoscience & Nanotechnology)We show that boron-doped epitaxial graphene can be successfully grown by thermal decomposition of a boron carbide thin film, which can also be epitaxially grown on a silicon carbide substrate. The interfaces of BC on SiC and graphene on BC had a fixed orientation relation, having a local stable structure with no dangling bonds. The first carbon layer on BC acts as a buffer layer, and the overlaying carbon layers are graphene. Graphene on BC was highly boron doped, and the hole concentration could be controlled over a wide range of 2
10
to 210
cm
. Highly boron-doped graphene exhibited a spin-glass behavior, which suggests the presence of local antiferromagnetic ordering in the spin-frustration system. Thermal decomposition of carbides holds the promise of being a technique to obtain a new class of wafer-scale functional epitaxial graphene for various applications.
*
JNC TN9440 2000-002, 157 Pages, 2000/02
JNC-TN9440-2000-002.pdf:5.44MB
This report summarizes the operating and irradiation data of the experimental reactor "JOYO" 33rd cycle, and estimates the 34th cycle irradiation condition. Irradiation tests in the 33rd cycle are as follows: (1)B-type irradiation rig (B9) (a)High burn up performance tests of "MONJU" fuel pins, advanced austenitic steel cladding fuel pins, large diameter fuel pins, ferrite steel cladding fuel pins and large diameter annular pellet fuel pins (b)Mixed carbide and nitride fuel pins irradiation tests (in collaboration with JAERI) (2)C-type irradiation rig (C4F) (a)High burn up performance test of advanced austenitic stainless steel cladding fuel pins (in collaboration with France) (3)C-type irradiation rig (C6D) (a)Large diameter fuel pins irradiation tests (4)Absorber Materials Irradiation Rig (AMIR-6) (a)Run to absorber pin's cladding breach (5)Core Materials Irradiation Rig (CMIR-5) (a)Cladding tube materials irradiation tests for "MONJU" (6)Core Materials Irradiation Rig (CMIR-5-1) (a)Core materials irradiation tests (7)Structure Materials Irradiation Rigs(SMIR) (a)Material irradiation tests (in collaboration with universities) (b)Surveillance back up tests for "MONJU" (8)Upper core structure Irradiation Plug Rig (UPR-1-5) (a)Upper core neutron spectrum effect and accelerated irradiation effect. The maximum burnup driver assembly "PFD516" reached 64,300MWd/t (pin average).
Suzuki, Yasufumi
Nihon Genshiryoku Gakkai-Shi, 41(4), p.376 - 377, 1999/04
no abstracts in English
JAERI-Review 98-011, 151 Pages, 1998/03
JAERI-Review-98-011.pdf:6.69MB
no abstracts in English
Suzuki, Yasufumi; Arai, Yasuo
Purutoniumu Nenryo Kogaku; Nihon Genshiryoku Gakkai "Jisedai Nenryo" Kenkyu Semmon Iinkai, p.260 - 291, 1998/00
no abstracts in English
Iwai, Takashi; Nakajima, Kunihisa; Arai, Yasuo;
IAEA-TECDOC-970, 0, p.137 - 153, 1997/10
no abstracts in English
Suzuki, Yasufumi; Arai, Yasuo; Iwai, Takashi; Nakajima, Kunihisa
Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 1, p.522 - 527, 1997/00
no abstracts in English
Iwai, Takashi; Arai, Yasuo; Nakajima, Kunihisa; Kimura, Yasuhiko; ;
JAERI-Research 96-066, 26 Pages, 1996/12
JAERI-Research-96-066.pdf:1.91MB
no abstracts in English
Iwai, Takashi; Arai, Yasuo; Nakajima, Kunihisa; Kimura, Yasuhiko; ;
JAERI-Research 96-065, 47 Pages, 1996/12
JAERI-Research-96-065.pdf:4.1MB
no abstracts in English
Arai, Yasuo; Iwai, Takashi; ; Okamoto, Yoshihiro; Shiozawa, Kenichi;
JAERI-Research 96-009, 17 Pages, 1996/02
JAERI-Research-96-009.pdf:1.09MB
no abstracts in English
Nishi, Hiroshi
JAERI-Research 94-031, 14 Pages, 1994/11
JAERI-Research-94-031.pdf:0.92MB
no abstracts in English
Arai, Yasuo; Iwai, Takashi; ; Nakajima, Kunihisa; ; ;
JAERI-Research 94-027, 66 Pages, 1994/11
JAERI-Research-94-027.pdf:4.09MB
no abstracts in English
Iwai, Takashi; Arai, Yasuo; Maeda, Atsushi; ; ; ;
JAERI-M 94-036, 81 Pages, 1994/03
no abstracts in English
Iwai, Takashi; ; Maeda, Atsushi; ; Handa, Nuneo
Nihon Genshiryoku Gakkai-Shi, 34(5), p.455 - 467, 1992/05
Times Cited Count：1 Percentile：17.26(Nuclear Science & Technology)no abstracts in English
; Arai, Yasuo; ; Maeda, Atsushi; Iwai, Takashi; Omichi, Toshihiko; Handa, Nuneo
Nihon Genshiryoku Gakkai-Shi, 34(1), p.66 - 74, 1992/01
Times Cited Count：1 Percentile：17.26(Nuclear Science & Technology)no abstracts in English
