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JAEA Reports

Effect of neptunium ions on corrosion of stainless steel in nitric acid solution

Motooka, Takafumi; Ishikawa, Akiyoshi; Numata, Masami; Endo, Shinya; Itonaga, Fumio; Kiuchi, Kiyoshi; Kizaki, Minoru

JAEA-Research 2007-031, 20 Pages, 2007/03

JAEA-Research-2007-031.pdf:2.0MB

An effect of neptunium ions on corrosion of stainless steel in nitric acid solution was investigated by corrosion tests. Type SUS304L stainless steel was used for the tests. The corrosion tests were conducted in 9kmol/m$$^{3}$$ nitric acid solutions containing neptunium ions, where test specimens were immersed or heat-transferred. As a result, we found that neptunium ions promote corrosion of stainless steels in nitric acid solution. This finding would contribute to modifications of the materials for spent fuel reprocessing process.

Journal Articles

PIE technique of fuel cladding fracture toughness test

Endo, Shinya; Usami, Koji; Nakata, Masahito; Fukuda, Takuji*; Onozawa, Atsushi; Harada, Akio; Kizaki, Minoru; Kikuchi, Hiroyuki

HPR-366, Vol.1 (CD-ROM), 10 Pages, 2007/03

no abstracts in English

Journal Articles

Diffusive transport of neptunium and plutonium through compacted sand-bentonite mixtures under anaerobic conditions

Yamaguchi, Tetsuji; Nakayama, Shinichi; Nagao, Seiya*; Kizaki, Minoru

Radiochimica Acta, 95(2), p.115 - 125, 2007/02

 Times Cited Count:6 Percentile:53.53(Chemistry, Inorganic & Nuclear)

Diffusive transport of neptunium, plutonium, tritiated water, Cs$$^{+}$$ and I$$^{-}$$ in compacted sand-bentonite mixtures was studied by a through diffusion method. Experiments for Np were performed in the presence of carbonate where Np was stable as Np$$^{IV}$$(CO$$_{3}$$)$$_{2}$$(OH)$$_{2}$$$$^{2-}$$ and those for Pu in the presence of fulvic acid where the Pu was stable as fulvic complexes. These experiments were performed under Ar (${it p}$ $$_{O2}$$ $$<$$ 10$$^{-6}$$ atm). Effective diffusivity (De) values of (1.81$$pm$$0.03)$$times$$10$$^{-10}$$, (1.8$$pm$$0.8)$$times$$10$$^{-10}$$, (5.1$$pm$$0.8)$$times$$10$$^{-11}$$ and (9.0$$pm$$4.1)$$times$$10$$^{-11}$$ m$$^{2}$$ s$$^{-1}$$ were obtained for HTO, Cs$$^{+}$$, I$$^{-}$$ and Np$$^{IV}$$(CO$$_{3}$$)$$_{2}$$(OH)$$_{2}$$$$^{2-}$$, respectively. The ratio of the De to the diffusivity in bulk of the water was around 0.1 for Np$$^{IV}$$(CO$$_{3}$$)$$_{2}$$(OH)$$_{2}$$$$^{2-}$$, HTO and Cs$$^{+}$$, which is consistent with the pore diffusion model. Observed diffusive transport of Pu was much smaller than those of HTO, Cs$$^{+}$$, I$$^{-}$$ and Np$$^{IV}$$(CO$$_{3}$$)$$_{2}$$(OH)$$_{2}$$$$^{2-}$$ probably because Pu was present as colloidal forms and that confined pore space in the compacted sand-bentonite mixtures does not allow diffusive transport of colloidal plutonium.

Journal Articles

Thermal diffusivity of Americium mononitride from 373 to 1473 K

Nishi, Tsuyoshi; Takano, Masahide; Ito, Akinori; Akabori, Mitsuo; Minato, Kazuo; Kizaki, Minoru

Journal of Nuclear Materials, 355(1-3), p.114 - 118, 2006/09

 Times Cited Count:20 Percentile:17.34(Materials Science, Multidisciplinary)

The thermal diffusivity of AmN was measured from 373 to 1473 K by a laser flash method. The AmN sample was prepared from AmO$$_{2}$$ by the carbothermic reduction. The obtained AmN product was grinded and pressed at about 400 MPa to form a disk. The disk was sintered at 1823 K for 10 hours in flowing N$$_{2}$$+4%H$$_{2}$$ gas. The thermal diffusivity slightly decreased from 3.4$$times$$10$$^{-6}$$ to 2.8$$times$$10$$^{-6}$$ m$$^{2}$$/s with increasing temperature. As the specific heat capacity of AmN was not available in literature, the thermal conductivity of AmN was tentatively estimated from the measured thermal diffusivity, bulk density and the specific heat capacity of PuN. It was found that the thermal conductivity of AmN slightly increased with temperature. The thermal conductivity of AmN corrected to 100%TD was found to be smaller than those of UN, NpN and PuN, whereas that of AmN was larger than those of UO$$_{2}$$ and (U$$_{0.8}$$Pu$$_{0.2}$$)O$$_{2}$$.

Journal Articles

PIE technologies for the study of stress corrosion cracking of reactor structural materials

Ugachi, Hirokazu; Nakano, Junichi; Nemoto, Yoshiyuki; Kondo, Keietsu; Miwa, Yukio; Kaji, Yoshiyuki; Tsukada, Takashi; Kizaki, Minoru; Omi, Masao; Shimizu, Michio

JAEA-Conf 2006-003, p.253 - 265, 2006/05

Irradiation assisted stress corrosion cracking (IASCC) is one of the critical concerns when stainless steel components have been in service in the light water reactors (LWRs) for a long period. In general, IASCC can be reproduced on the materials irradiated over a certain threshold fluence level of fast neutron by the post-irradiation examinations (PIEs) at hot laboratories. On the other hand, recently in the Japanese boiling water reactor (BWR) power plants, many incidents of stress corrosion cracking (SCC) of structural material such as the reactor core shrouds and primary loop recirculation (PLR) system piping were reported. In order to investigate the cause of SCC, PIEs at hot laboratories were carried out on the sample material extracted from BWR power plants. SCC studies require various kind of PIE techniques, because the SCC is caused by a complicated synergistic effects of stress and chemical environment on material that suffered degradations by irradiation and/or thermal aging. In this paper, we describe the PIE techniques adopted recently for our SCC studies, especially the crack growth measurement, uniaxial constant load (UCL) tensile test method, in-situ observation during slow strain rate test (SSRT) and several metallurgical test techniques using the FEtype transmission electron microscopy (FE-TEM), focused ion beam (FIB) processing technique, three Dimensional Atom Probe (3DAP) analysis and atomic force microscopy (AFM).

JAEA Reports

Study on high-performance fuel cladding materials; Joint research report in FY 2001-2005 (Phase 2) (Joint research)

Kiuchi, Kiyoshi; Ioka, Ikuo; Tanabe, Makoto*; Nanjo, Yoshiyasu*; Ogawa, Hiroaki; Ishijima, Yasuhiro; Tsukatani, Ichiro; Ochiai, Takamasa; Kizaki, Minoru; Kato, Yoshiaki; et al.

JAEA-Research 2006-023, 173 Pages, 2006/03

JAEA-Research-2006-023.pdf:20.51MB

The research concerning new cladding materials for ultra-high burnup of fuel elements with MOX fuels aiming at 100 GWd/t of BWR was pursued for 5 years from 2001 to 2005. On the Phase 1, the modified stainless steel of Fe-25Cr-35Ni-0.2Ti as fuel claddings and Nb-Mo alloy as a liner for inhibiting the pellet- clad interaction were selected as candidate materials, by evaluating fundamental properties required to BWR cladding materials, that are the nuclear economy, radioactivity, mass-transfer, irradiation properties, mechanical properties so on. On the present study, the making process of cladding tubes, lining by diffusion bonding, end plug by laser welding were developed and optimized, by considering the practical use of fuel elements consists of these candidates. The practical applicability was basically examined by irradiation tests using the accelerator of TIARA and the research reactor of JRR-3, for mainly confirming the resistance to IGSCC as one of the current important issues of BWR core materials of low carbon grade stainless steels. Creep and fatigue testing data were also obtained for evaluating the long performance of candidate materials. The behavior as fuel elements was analyzed with the safety calculation code for BWRs. The obtained results were established as a data base system, by considering the applicability to the fuel design and in-pile loop tests.

Journal Articles

Operation and utilization of Waste Safety Testing Facility

Kizaki, Minoru

Genshiryoku Hyakka Jiten ATOMICA (Internet), 4 Pages, 2006/00

no abstracts in English

Journal Articles

PIE technique of LWR fuel cladding fracture toughness test

Endo, Shinya; Usami, Koji; Nakata, Masahito; Fukuda, Takuji*; Numata, Masami; Kizaki, Minoru; Nishino, Yasuharu

Proceedings of 2005 JAEA-KAERI Joint Seminar on Advanced Irradiation and PIE Technologies, p.S2_7_1 - S2_7_11, 2005/11

no abstracts in English

JAEA Reports

Development and installation of thermal diffusivity measurement apparatus for minor actinide compounds (Contract research)

Nishi, Tsuyoshi; Takano, Masahide; Ito, Akinori; Akabori, Mitsuo; Minato, Kazuo; Kizaki, Minoru

JAERI-Tech 2005-051, 13 Pages, 2005/09

JAERI-Tech-2005-051.pdf:1.38MB

An apparatus has been developed to measure the thermal diffusivities of minor actinide (MA) compounds. By installing the laser flash apparatus in a glove box with highly purified inert gas atmosphere, the thermal diffusivities measurement of MA compounds of $$alpha$$-decay nuclides was enabled. A new sample holder has been also developed to measure the thermal diffusivities of very small samples. The performance of this new apparatus was confirmed by measuring the thermal diffusivities of small samples of tantalum, nickel and cerium oxides. The thermal diffusivity values obtained in this work agreed well with the literature values and the values measured by a conventional thermal diffusivities measurement apparatus. Accordingly, this apparatus was found to be useful for thermal diffusivities measurement of MA compounds.

Journal Articles

Lattice parameter expansion by self-irradiation damage of $$^{244}$$Cm-$$^{240}$$Pu oxide and mononitride

Takano, Masahide; Ito, Akinori; Akabori, Mitsuo; Ogawa, Toru; Numata, Masami; Kizaki, Minoru

Journal of Nuclear Science and Technology, 39(Suppl.3), p.842 - 845, 2002/11

no abstracts in English

JAEA Reports

PIE technology on mechanical tests for HTTR core component and structural materials developed at research hot laboratory

Kizaki, Minoru; Honda, Junichi; Usami, Koji; Ouchi, Asao*; Oeda, Etsuro; Matsumoto, Seiichiro

JAERI-Tech 2000-087, 50 Pages, 2001/02

JAERI-Tech-2000-087.pdf:2.78MB

no abstracts in English

Journal Articles

Development of examination apparatus for miniaturized specimen tests

Saito, Junichi; ; Jitsukawa, Shiro; ; Omi, Masao; Kizaki, Minoru

KAERI-NEMAC/TR-32/95, 0, p.210 - 219, 1995/00

no abstracts in English

JAEA Reports

Irradiation experiments of low copper A533B steels for reactor pressure vessel tested in JMTR

Suzuki, Masahide; Onizawa, Kunio; Kizaki, Minoru

JAERI-Research 94-015, 74 Pages, 1994/09

JAERI-Research-94-015.pdf:1.59MB

no abstracts in English

Journal Articles

Research and development on materials as base technology in nuclear applications

Kondo, Tatsuo; Hishinuma, Akimichi; Noda, Kenji; Eto, Motokuni; Tsuji, Hirokazu; Nakajima, Hajime; Kiuchi, Kiyoshi; Ono, Hideo; Ogawa, Toru; Omichi, Hideki; et al.

Genshiryoku Kogyo, 39(8), p.1 - 80, 1993/08

no abstracts in English

Journal Articles

Methods and devices for small specimen testing at the Japan Atomic Energy Research Institute

Jitsukawa, Shiro; Kizaki, Minoru; ; Shiba, Kiyoyuki; Hishinuma, Akimichi

Small Specimen Test Techniques; ASTM STP 1204, p.289 - 307, 1993/00

 Times Cited Count:13 Percentile:1.67

no abstracts in English

JAEA Reports

Facility for stress corrosion cracking test of irradiated material in high temperature water

Tsukada, Takashi; Shiba, Kiyoyuki; G.E.C.Bell*; Nakajima, Hajime; Kizaki, Minoru; Omi, Masao; Sudo, Kenji; Goto, Ichiro

JAERI-M 92-081, 27 Pages, 1992/06

JAERI-M-92-081.pdf:1.73MB

no abstracts in English

Journal Articles

Post irradiation test facilities for irradiation assisted stress corrosion cracking research

Tsukada, Takashi; Shiba, Kiyoyuki; Omi, Masao; Kizaki, Minoru; ; Nakajima, Hajime

Proc. of the 3rd Asian Symp. on Research Reactor, 8 Pages, 1991/00

no abstracts in English

JAEA Reports

Development of the remote-controlled electrical resistance measurement apparatus

Hoshiya, Taiji; ; Kizaki, Minoru; *; Sudo, Kenji; ;

JAERI-M 89-205, 68 Pages, 1989/12

JAERI-M-89-205.pdf:1.8MB

no abstracts in English

JAEA Reports

Iodine-SCC behavior of irradiated zircaloy-2 cladding under changing

Suzuki, Motoe; Kizaki, Minoru;

JAERI-M 88-217, 60 Pages, 1988/11

JAERI-M-88-217.pdf:5.0MB

no abstracts in English

Oral presentation

Thermal conductivity of americium oxide

Nishi, Tsuyoshi; Takano, Masahide; Ito, Akinori; Akabori, Mitsuo; Minato, Kazuo; Kizaki, Minoru

no journal, , 

no abstracts in English

24 (Records 1-20 displayed on this page)