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Journal Articles

The Effects of plutonium content and self-irradiation on thermal conductivity of mixed oxide fuel

Ikusawa, Yoshihisa; Morimoto, Kyoichi; Kato, Masato; Saito, Kosuke; Uno, Masayoshi*

Nuclear Technology, 205(3), p.474 - 485, 2019/03

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

This study evaluated the effects of plutonium content and self-irradiation on the thermal conductivity of mixed-oxide (MOX) fuel. Samples of UO$$_{2}$$ fuel and various MOX fuels were tested. The MOX fuels had a range of plutonium contents, and some samples were stored for 20 years. The thermal conductivity of these samples was determined from thermal diffusivity measurements taken via laser flash analysis. Although the thermal conductivity decreased with increasing plutonium content, this effect was slight. The effect of self-irradiation was investigated using the stored samples. The reduction in thermal conductivity caused by self-irradiation depended on the plutonium content, its isotopic composition, and storage time. The reduction in thermal conductivity over 20 years' storage can be predicted from the change of lattice parameter. In addition, the decrease in thermal conductivity caused by self-irradiation was recovered with heat treatment, and recovered almost completely at temperatures over 1200 K. From these evaluation results, we formulated an equation for thermal conductivity that is based on the classical phonon-transport model. This equation can predict the thermal conductivity of MOX fuel thermal conductivity by accounting for the influences of plutonium content and self-irradiation.

Journal Articles

Isotope-selective microscale imaging of radioactive Cs without isobaric interferences using sputtered neutral mass spectrometry with two-step resonant ionization employing newly-developed Ti:Sapphire lasers

Sakamoto, Tetsuo*; Morita, Masato*; Kanenari, Keita*; Tomita, Hideki*; Sonnenschein, V.*; Saito, Kosuke*; Ohashi, Masaya*; Kato, Kotaro*; Iguchi, Tetsuo*; Kawai, Toshihide*; et al.

Analytical Sciences, 34(11), p.1265 - 1270, 2018/11

 Times Cited Count:4 Percentile:67.24(Chemistry, Analytical)

JAEA Reports

Study on characterisation of colloidal silica grout under condition of sea water

Toguri, Satohito*; Okihara, Mistunobu*; Tsuji, Masakuni*; Nakashima, Hitoshi*; Sugiyama, Hirokazu*; Saito, Akira*; Sato, Toshinori; Aoyagi, Kazuhei; Masunaga, Kosuke

JAEA-Research 2017-013, 131 Pages, 2018/02

JAEA-Research-2017-013.pdf:8.49MB

The discussions on scientifically promising site for the geological disposal has been made at the council of studying group on techniques for geological disposal of radioactive wastes, which is held by Resources and Energy Agency. From the aspect of ensuring safety during the transportation of disposal waste, the coastal area is discussed to be a more suitable area. This report shows the result of the first year of this project as following items; Study on the state-of-art technology and remain tasks; laboratory tests on characterization of colloidal silica grout under sea water; Study on the development of grouting technology (design and the evaluation method of influence on the rock mass).

Journal Articles

Electronic stopping power connected with average charge reduction for swift carbon cluster ions in carbon

Kaneko, Toshiaki*; Ihara, Kosuke*; Kono, Maasa*; Saito, Yuichi; Chiba, Atsuya; Narumi, Kazumasa

JAEA-Review 2012-046, JAEA Takasaki Annual Report 2011, P. 164, 2013/01

JAEA Reports

Alpha-ray irradiation damage on diverse rubber materials applied to glove box for plutonium treatment

Saito, Kosuke; Nogami, Yoshitaka; Kodato, Kazuo; Matsuyama, Kazutomi; Endo, Hideo

JAEA-Research 2012-027, 118 Pages, 2012/09

JAEA-Research-2012-027.pdf:21.12MB

This report is compilation of 4 years tests and experiments of simulated alpha-ray irradiation on diverse materials for glove box application at Plutonium Fuel Development Center, Tokai, JAEA. Specimens prepared from the materials are irradiated with $$^{4}$$He$$^{2+}$$ ion beam whose kinetic energy was 5 MeV and sent to exterior observation, optical microscopy and tensile tests. Experiments revealed ion-irradiation generally makes tens of micrometers of deteriorated layer which is hardened and discolored on the surface of the specimens. According to dose, tensile properties such as tensile strength and elongation at break decrease generally. Tensile strength decrease is expected to ascribe to stress concentration on cracks of irradiation-damaged surface and rupture. Lead-contained glove, which is ordinarily used on highly $$gamma$$-radiative environments, saturates the decrease of its tensile strength around fluence of 1.4e+14 cm$$^{-2}$$. In addition, deterioration was accelerated for tension-loaded material and the saturation is around 4.6e+13 cm$$^{-2}$$ for 100%-extended specimens. The candidates of alternative new materials are two kinds of developed chlorosulfonated polyethylene (CSM) and conductive rubber, which were experimented and tested in like manner. From the results and inherent properties of these materials, one kind of CSM and conductive rubber are relatively promising. Gloves used at low-dose environments and vinyl chloride applied for glove ports were also experimented and tested, and quantitative data were which are useful for life-elongation measure obtained. The irradiation tests on this report are unprecedented ones with low-energy ion, and the obtained quantitative data of material properties and deterioration are scientifically rare and important.

Journal Articles

The H-Invitational Database (H-InvDB); A Comprehensive annotation resource for human genes and transcripts

Yamasaki, Chisato*; Murakami, Katsuhiko*; Fujii, Yasuyuki*; Sato, Yoshiharu*; Harada, Erimi*; Takeda, Junichi*; Taniya, Takayuki*; Sakate, Ryuichi*; Kikugawa, Shingo*; Shimada, Makoto*; et al.

Nucleic Acids Research, 36(Database), p.D793 - D799, 2008/01

 Times Cited Count:50 Percentile:23.98(Biochemistry & Molecular Biology)

Here we report the new features and improvements in our latest release of the H-Invitational Database, a comprehensive annotation resource for human genes and transcripts. H-InvDB, originally developed as an integrated database of the human transcriptome based on extensive annotation of large sets of fulllength cDNA (FLcDNA) clones, now provides annotation for 120 558 human mRNAs extracted from the International Nucleotide Sequence Databases (INSD), in addition to 54 978 human FLcDNAs, in the latest release H-InvDB. We mapped those human transcripts onto the human genome sequences (NCBI build 36.1) and determined 34 699 human gene clusters, which could define 34 057 protein-coding and 642 non-protein-coding loci; 858 transcribed loci overlapped with predicted pseudogenes.

JAEA Reports

Design study on a demonstration core for a practical LMFBR in Monju, 2

Saito, Kosuke; Maeda, Seiichiro; Higuchi, Masashi*; Takano, Mitsuhiro*; Nakazawa, Hiroaki

JAEA-Technology 2006-035, 76 Pages, 2006/06

JAEA-Technology-2006-035.pdf:5.25MB

Because of the revision on the standardized strength of the ODS steel, the previous design study of MONJU demonstrative core has been obliged to be reconsidered. For economical advantages, only a 127 pins-bundle core was selected to be redesigned. For the sake of cladding endurance, the ratio of cladding thickness to outer diameter was reset incrementally followed by the determination of the basic specification of a pin. Notwithstanding some deterioration thanks to the reduction of a fuel volume fraction, the prospect in neutronics was obtained. Coolant flow distribution design which was based on power distribution was successfully carried out without overheating cladding. Average burn-up of 150 GWd/t and 380 days-long operational period per cycle are to be attained, and the designed core can thermally afford to receive test fuels. The study has necessity to be advanced extensively for the purpose of materialization according to the circumstances of MONJU in future.

Oral presentation

Prototype FBR Monju system start up test "zero power reactor physics test", 5; Applicability of sub-criticality measurement methods

Kitano, Akihiro; Mori, Tetsuya; Nagata, Akito*; Saito, Kosuke; Misawa, Tsuyoshi*; Tamagawa, Yoichi*

no journal, , 

no abstracts in English

Oral presentation

Gas generation by $$gamma$$-ray irradiation to polyethylene, polystyrene and cellulose resin

Saito, Kosuke

no journal, , 

At 23rd July 2010, a fire accident broke out in Plutonium Fuel Development Center (Pu Center), Tokai, JAEA. The fire was occurred from the cylindrical container of stainless steel in a glove box which loaded uranium and plutonium compounds. In order to clear up the cause of the fire, Pu Center studied it from all angles. For one of the possible causes, some inflammable gas and/or hydrogen gas were deduced to be generated from irradiated plastic cases and/or cellulose resin which are organic substances in the stainless container. The plastic cases, which were used to reposit nuclear materials, are made of both polyethylene (PE) and polystyrene (PS). The both polymer was known to be decomposed by $$gamma$$-ray irradiation and generate hydrogen gas, whose quantitative evaluation as absorbed dose was reported. As for PE, other gases such as carbon oxides, methane and ethane are produced. Cellulose resin was used for binder of uranium nitride powder, but gas generation from cellulose resin by $$gamma$$-ray irradiation has not been reported. Then, in order to demonstrate and investigate hydrogen and inflammable-gas generation from polymers and cellulose resins, $$gamma$$-ray irradiation to the materials and analyses of the generated gaseous substances were performed.

Oral presentation

Average-charge reduction and energy loss for swift cluster ion

Kaneko, Toshiaki*; Ihara, Kosuke*; Kono, Maasa*; Saito, Yuichi; Chiba, Atsuya; Narumi, Kazumasa

no journal, , 

no abstracts in English

Oral presentation

Blanket fuel with high proliferation resistance in fast breeder reactor; Pu production behavior in MOX fuel

Onishi, Takashi; Tanaka, Kosuke; Koyama, Shinichi; Sagara, Hiroshi*; Han, C. Y.*; Saito, Masaki*

no journal, , 

no abstracts in English

Oral presentation

Countermeasure against plant root intrusion into capping in Ningyo-toge Environmental Engineering Center

Masunaga, Kosuke; Saito, Hiroshi; Sato, Hisakazu*

no journal, , 

Ningyo-toge Environmental Engineering Center has carried out remediation activities for Ningyo-toge Uranium Mine, now out of service for mining in accordance with the Mine Safety Law, to ensure the radiation protection from the exposure pathways to humans in future and to prevent the occurrence of mining pollution. Some remediation activities has already done so far, including capping construction for the upstream of mill tailings pond by the end of FY2012. The purpose of the capping is to reduce dose rate radon exhalation rate and rain infiltration rate of the pond, which is considered as the most prioritized facility to remediate.Post-remedial maintenance must be reduced just like to lower the burden of water treatment in future by capping construction as is written above. For the reason, plant root intrusion, its long-term impact to the function of the capping and countermeasure have been studied as plant is expected to intrude into the pond through its surface as capping. The result shows that annual herbs will intrude followed by perennials herbs and woody plants which constitutes forest eventually. Also, it is estimated that the long-time duration makes it easier for woody plants to intrude before vegetation becomes dense if vegetation is subject to natural succession. For these reasons, controlled vegetation is thought to be suitable compared with natural vegetation. Also, in terms of factors including economy, tolerance to cold climate and root depth, grass-felt with the seedlings of Gramineae is chosen as most suitable countermeasure against erosion.

Oral presentation

Study on characterization of liquid-type colloidal silica grout under sea water, 1; Outline of study

Masunaga, Kosuke; Sato, Toshinori; Okihara, Mistunobu*; Tsuji, Masakuni*; Nakashima, Hitoshi*; Saito, Akira*

no journal, , 

Study on characterization of liquid-type colloidal silica grout under sea water has been performed for the countermeasures against water inflow in the underground construction. This report shows the outline of this study.

Oral presentation

Study on characterization of liquid-type colloidal silica grout under sea water, 3; Result of laboratory test

Nakashima, Hitoshi*; Okihara, Mistunobu*; Tsuji, Masakuni*; Saito, Akira*; Sato, Toshinori; Masunaga, Kosuke

no journal, , 

Study on characterization of liquid-type colloidal silica grout under sea water has been performed. This report shows the results of laboratory tests.

Oral presentation

Development of automatic detection and measurement system for the Pu spot in the MOX fuel pellet

Tazawa, Yuto; Hosogane, Tatsuya; Ishikawa, Fumitaka; Kayano, Masashi; Matsuyama, Kazutomi; Saito, Kosuke; Oishi, Shinichi*; Nakajima, Hiroshi*

no journal, , 

no abstracts in English

Oral presentation

Resonant laser secondary neutral mass spectrometry for micro imaging of radioactive isotopes, 2

Tomita, Hideki*; Saito, Kosuke*; Ohashi, Masaya*; Sonnenschein, V.*; Kato, Kotaro*; Suzuki, So*; Iguchi, Tetsuo*; Morita, Masato*; Sakamoto, Tetsuo*; Kanenari, Keita*; et al.

no journal, , 

no abstracts in English

Oral presentation

Study on characterisation of colloidal silica grout under sea water, 4; Basic prope rties of two types of new grout mix adapted to sea water

Nakashima, Hitoshi*; Saito, Akira*; Tsuji, Masakuni*; Sato, Toshinori; Aoyagi, Kazuhei; Masunaga, Kosuke*

no journal, , 

Study on characterization of liquid-type colloidal silica grout under sea water has been performed. This report shows the results of laboratory tests.

17 (Records 1-17 displayed on this page)
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