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Tanaka, Kosuke; Miwa, Shuhei; Sato, Isamu; Osaka, Masahiko; Hirosawa, Takashi; Obayashi, Hiroshi; Koyama, Shinichi; Yoshimochi, Hiroshi; Tanaka, Kenya
Actinide and Fission Product Partitioning and Transmutation, p.179 - 187, 2010/00
In order to investigate the effect of americium addition to MOX fuels on the irradiation behavior, the "Am-1" program is being conducted in JAEA. The Am-1 program consists of two short-term irradiation tests of 10-minute and 24-hour irradiations and a steady-state irradiation test. The short-term irradiation tests were successfully completed and the post irradiation examinations (PIEs) are in progress. The PIEs for Am-containing MOX fuels focused on the microstructural evolution and redistribution behavior of Am at the initial stage of irradiation and the results to date are reported. Successful development of fabrication technology with remote handling and evaluation of thermo-chemical properties based on the out-of-pile experiments are described with an emphasis on the effects of Am addition on the MOX fuel properties.
Hayashi, Hirokazu; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 9 Pages, 2010/00
R&D on the transmutation of long-lived minor actinides (MA) by the accelerator-driven system (ADS) using nitride fuels is underway at JAEA. In regard to reprocessing technology, pyrochemical process has several advantages in case of treating spent fuel with large decay heat and fast neutron emission, and recovering highly enriched 
N. In the pyrochemical reprocessing, plutonium and MA are dissolved in LiCl-KCl eutectic melts and selectively recovered into liquid cadmium cathode by molten salt electrorefining. The electrochemical behavior in LiCl-KCl eutectic melts and the subsequent nitride formation behavior of plutonium and MA recovered in liquid Cd cathode are investigated. Recent results on the behavior of americium (Am) in the pyrochemical process for the treatment of spent nitride fuel, which include preparation of AmCl
and electrochemical behavior of Am in LiCl-KCl eutectic melts, are presented.
Kato, Masato; Morimoto, Kyoichi; Komeno, Akira; Nakamichi, Shinya; Kashimura, Motoaki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), p.201 - 209, 2010/00
Japan Atomic Energy Agency has developed homogeneous MOX fuel containing minor actinide (MA) elements such as Np and Am. To measure physical properties of the fuel is essential for its development, because their data are needed to evaluate irradiation behavior. In this report, the physical properties, melting temperature, thermal conductivity, lattice parameter, oxygen potential and phase separation behavior, were reviewed, and effect of MA content was discussed.
Sugawara, Takanori; Suzuki, Kazuhiko; Nishihara, Kenji; Sasa, Toshinobu; Kurata, Yuji; Kikuchi, Kenji; Oigawa, Hiroyuki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 11 Pages, 2010/00
The investigations of the beam window which is one of the most critical components for the Accelerator Driven System (ADS) were performed. In the previous study, it was found that the buckling failure was the most severe failure mode for the beam window. Hence, the shape and the thickness of the beam window were optimized to prevent the buckling failure. The buckling analyses with initial imperfections were also performed to identify the level of the factor of safety (FS). The results showed that FS of 3 was conservative enough to ensure the integrity of the beam window. It was also shown that the ellipse shape concepts with the thickness of 2.0-2.4[mm] at the top and the thickness of 2.0-4.0[mm] at the transient part were acceptable under the current ADS design parameters.
Sugawara, Takanori; Sasa, Toshinobu; Oigawa, Hiroyuki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 10 Pages, 2010/00
Improvement on the neutronics design accuracy of the MA-loaded core is one of the most important issues in the MA transmutation technologies. Uncertainties of the current MA nuclear data are supposed to be larger than those of other major nuclides. Therefore, analyzed neutronics properties of MA-loaded FR and ADS have much larger design margins in comparison with those of conventional FR. To improve the reliability, safety and economical efficiency of these systems, it is required to increase the accuracy of the nuclear data of MA by the experimental data taken under adequate experimental conditions. In this study, error analyses were conducted to estimate the benefit of the MA-loaded experiments at TEF-P (Transmutation Physics Experimental Facility) on the error reduction in neutronics design of transmutation systems. Through this estimation, the effect of the MA-loaded experiments at TEF-P was verified quantitatively.
Kurata, Yuji; Saito, Shigeru
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 11 Pages, 2010/00
Corrosion tests of various steels in liquid Pb-Bi have been conducted using static corrosion apparatus to study corrosion behaviour in liquid Pb-Bi, a promising candidate material of coolants and high-power spallation targets of accelerator driven systems for transmutation of radioactive wastes. Effects of temperature, oxygen concentration in Pb-Bi and elements in steels on corrosion behavior were estimated from test results. Tested temperature range was from 450
C to 600C. Temperature increase produced active corrosion and grain boundary corrosion, penetration of Pb-Bi and ferritization became severe above 550C. Effect of oxygen concentration was clearly found in pure iron and 316SS at 450C and corrosion attack became severe under the low oxygen concentration condition at 550C. Mod.9Cr-1Mo with addition of 1.5%Si and 316SS with addition of 2.5%Si showed good corrosion resistance in liquid oxygen-saturated Pb-Bi at 550C.
-tetradodecyl-diglycolamideSasaki, Yuji; Asakura, Toshihide; Kitatsuji, Yoshihiro; Morita, Yasuji; Kimura, Takaumi
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 6 Pages, 2010/00
Diglycolamide, DGA, compounds have the strong extractability with trivalent, tetravalent and hexavalent actinides (An) from nitric acid to n-dodecane. Since DGA connecting with the long alkyl chain, TDdDGA (-tetradodecyl-diglycolamide), has the high extraction capacity and suppresses to form the third phase with Nd, we used TDdDGA to demonstrate the counter-current extraction, prior to the hot test. In this experiment we use four elements, i.e., Sr, Pd, Zr and Nd, as the typical fission products and a representative ion of An(III) and lanthanides, to confirm the extraction and the separation properties, these four elements are extractable by TDdDGA. After determination of the optimum condition on the extraction and separation of Nd from other elements by the calculation using D values, we perform the counter-current extraction using the mixer-settler equipment.
Takano, Masahide; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 7 Pages, 2010/00
As the research activities concerning the nitride fuel for the transmutation of minor actinides, the lattice thermal expansions of the transuranium nitrides were investigated in order to build the material database. The lattice parameters of NpN, PuN and AmN were measured by the high temperature X-ray diffraction method from room temperature to 1478 K. Their linear thermal expansions were determined as a function of temperature. The average thermal expansion coefficients over the temperature range of 293 to 1273 K for these nitrides were 8.8, 11.1 and 11.2
10
K
, respectively. Further, the thermal expansions of the nitride solid solution samples, (Np,Am)N, (Pu,Am)N, (Np,Pu,Am,Cm)N and (Pu,Am,Zr)N, were measured to investigate the composition dependence. It was confirmed that the average thermal expansion coefficients for these solid solution samples could be approximated by the linear mixture rule within the error of 2
3%.
Nishi, Tsuyoshi; Takano, Masahide; Ito, Akinori; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 8 Pages, 2010/00
Neptunium nitride (NpN) and americium nitride (AmN) were prepared by carbothermic reduction of the respective dioxides. The thermal diffusivities of NpN and AmN were measured by using a laser flash method. The heat capacities of NpN and AmN were determined with the drop calorimetry. The thermal diffusivity of NpN tends to remain unchanged with increasing temperature in the temperature range from 473 to 1473 K, and that of AmN tends to slightly decrease with increasing temperature in the same temperature range. The heat capacity of NpN obtained was close to those of UN and PuN, while that of AmN was slightly smaller than those of UN, NpN and PuN. The thermal conductivities of NpN and AmN were determined from the measured thermal diffusivities, heat capacities and bulk densities. It was found that the thermal conductivities of NpN and AmN slightly increased with temperature in the temperature range investigated.
Sato, Takumi; Iwai, Takashi; Arai, Yasuo
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 9 Pages, 2010/00
no abstracts in English
Kimura, Takaumi; Morita, Yasuji; Koma, Yoshikazu
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), p.243 - 249, 2010/00
no abstracts in English
Arai, Yasuo; Akabori, Mitsuo; Minato, Kazuo; Uno, Masayoshi*
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), p.189 - 197, 2010/00
The progress of R&D on nitride fuel and pyrochemical process for transmutation of minor actinides are described. Nitride fuel was prepared by carbothermic reduction and characterized by X-ray diffraction and chemical analyses. In addition to minor actinide nitrides, burnup simulated nitrides and nitrides with inert diluent materials were prepared, and the thermal properties such as thermal conductivity were obtained. With regard to pyrochemical process, the electrode behavior of the above nitrides in the molten salt was clarified, and nitride power synthesized from actinides recovered in liquid cadmium cathode was used for nitride pellet preparation. Further, the irradiation tests of nitride fuel carried out in JAEA are introduced.
Matsumura, Tatsuro; Takeshita, Kenji*; Inaba, Yusuke*; Mori, Atsunori*
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 6 Pages, 2010/00
no abstracts in English
Sasa, Toshinobu; Sugawara, Takanori; Nishihara, Kenji; Takei, Hayanori; Oigawa, Hiroyuki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), p.349 - 356, 2010/00
Construction of the Transmutation Experimental Facility (TEF) is planned within the framework of J-PARC project. In the current schedule, we are planning to install the critical assembly with a 30kW beam dump at the first phase and the lead-bismuth target facility with superconducting LINAC will be built at the latter phase. Based on this construction plan, JAEA collected the preliminary Letters Of Intent (LOI) for TEF. More than 30 research programs were proposed. According to these proposals, the re-arrangement of facility layout and the new experimental equipment design are now underway. One of the important developments is to prepare for the application of minor actinide fuels to critical assembly. The development of the technology to handle the high-background minor actinide fuel is being performed. Another important issue is the pulse operation of critical assembly under subcritical condition. The laser charge exchange technique and measurement system for pulse operation are also under development. The latest facility concept reflecting these efforts and user requests based on LOI will be introduced.
Sasa, Toshinobu; Nishihara, Kenji; Sugawara, Takanori; Oigawa, Hiroyuki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 9 Pages, 2010/00
The management of americium (Am) and Curium (Cm) in radioactive waste is one of the important issues for sustainable nuclear energy production. A concept of accelerator-driven system using liquid molten-salt fuel is proposed for the effective transmutation of Am and Cm. In the concept, Am and Cm are separated from the spent fuel and converted to chloride molten-salt fuel. Adopting such liquid-type fuel, many defects on Am and Cm such as high radioactivity and heat release and chemical incompatibility can be overcome. The system is an accelerator-driven system consists of a 10MW-class cyclotron, tungsten disk spallation target and subcritical core. The concept of molten-salt fueled accelerator-driven system and dedicated fuel cycle will be introduced.
Sasa, Toshinobu; Sugawara, Takanori; Fukahori, Tokio; Kosako, Kazuaki*
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 8 Pages, 2010/00
The latest version of JENDL High Energy File (JENDL/HE-2007) includes the reaction cross section of proton and neutron for 106 nuclides below 3 GeV to simulate accelerator application such as spallation neutron source and accelerator-driven system. A NJOY-99.251 code was modified to produce continuous energy cross section library for MCNPX code system from JENDL/HE-2007. Higher temperature libraries were also produced to simulate reactor systems accurately. Several test calculation was done with typical fast reactor and accelerator-driven transmutation system and good agreement was observed the k-effective values compared with existing JENDL-3.3 based cross section library.
Takei, Hayanori; Nishihara, Kenji; Tsujimoto, Kazufumi; Oigawa, Hiroyuki
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 7 Pages, 2010/00
no abstracts in English
Kikuchi, Kenji; Saito, Shigeru; Hamaguchi, Dai; Tezuka, Masao; Obayashi, Hironari
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), p.315 - 320, 2010/00
R&Ds to know materials performance and its limit for usage applying to the beam window of ADS are conducted by irradiation material test and lead bismuth flowing loop tests. Proton irradiation experiment showed ductility reduction and off-set stress increase in austenitic steels. Fracture mode change in ferritic-martensitic steels, 8-9 Cr steels. Fatigue test is under way in the hot cell. Microstructure analyses found that many bubbles exist in the materials. The relation between mechanical strength and nano-scale observation results is studied now. Corrosion of the materials under the lead bismuth flows showed local erosion-corrosion. A visualization technique has developed by using ultrasonic Doppler method and surface vitalizing techniques to inspect a local flow condition. Thermal fluid experiment was conducted to know heat transfer performance at the beam window, which will affect thermal loading magnitude. Experimental formula was established for design work.
Oigawa, Hiroyuki; Nishihara, Kenji; Nakayama, Shinichi; Morita, Yasuji
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), p.123 - 131, 2010/00
To illustrate the benefit of the partitioning and transmutation (PT) technology, several types of the waste management and the geological disposal concepts incorporating PT was discussed in terms of the repository size required to emplace the wastes. It was found that the transmutation of 
Am, which is a long-term heat source, is effective to prevent the inflation of the repository size expected in the case of plutonium utilization. If we intend to reduce the repository size to a larger extent the partitioning of Sr and Cs followed by their long-term (100 - 300 years) storage should be adopted together with the transmutation of MA.
Watanabe, Masayuki; Arisaka, Makoto; Kimura, Takaumi
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 5 Pages, 2010/00
N,N'-dimethyl-N,N'-diphenylpyridine-2,6-dicarboxyamide which contains a pyridyl group between two amidic functional groups exhibited moderate separation ability of actinides(III) from lanthanides(III) at high HNO
concentration by solvent extraction. To solve the leakage problem on the extraction chromatography, we reported that newly synthesized N,N'-dialkyl-N,N'-diphenylpyridine-2,6-dicarboxyamides (R-PDA; R = butyl, octyl, decyl, dodecyl) exhibited reduction on the leakage of extractant from the impregnated resin depending on the length of alkyl group. The column chromatography of actinides(III) from lanthanides (III) was investigated by using the impregnated resin with Oct-PDA.
