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Radiation-Induced Luminescence for Applying to Retrospective Dosimetry

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Radiation-Induced Luminescence for Applying to Retrospective...

作者： H.Fujita Y.Nakano T.Saito Nuclear Fuel Cycle Engineering Laboratories JAEA

INTRODUCTION:It is well known that natural quartz exposed to prior ionizing radiation emits luminescence by subsequent exposure to heat or light,i.e.,thermoluminescence (TL) or optically stimulated luminescence (OSL),respectively(e.g.).These luminescence signals have been widely applied to dating and retrospective *** characteristics of natural quartz are dependent on their origins, thermal histories,impurity contents,***, emission mechanism of luminescence from Japanese quartz has not been explained,so far.

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Development on In-Reactor Observation System Using Cherenkov Light

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Development on In-Reactor Observation System Using Cherenkov...

作者： K.Tsuchiya S.Kitagishi Y.Nagao N.Takemoto M.Naka A.Kimura T.Sano H.Unezaki T.Yoshimoto K.Nakajima Y.Fujiwara Y.Okumura S.Yamamoto Neutron Irradiation and Testing Reactor Center JAEA

INTRODUCTION:The Cherenkov light is a faint emission accompanying the passage of charged particles through a transparent medium at speeds faster than the speed of light in that *** high-energy gamma rays can generate high-velocity electrons by Compton scattering,Cherenkov light can be emitted as a result of gamma radiation fields as ***,the Cherenkov Viewing Device(CVD) was developed as an instrument specifically designed to form an image of the UV portion of this glow and it is used routinely by the

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Homogeneity tests on neutron shield concrete

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Nuclear Science and Techniques 2014年第A1期25卷 57-61页

作者： Koichi Okuno Hiroshi Iikura HAZAMA ANDO Technical Research Institute 515-1 Karima Tsukuba Ibaraki 305-0822 Japan jaea Quantum Beam Science Directorate 2-4 Shirakata Tokai-mura Naka-gun Ibaraki 319-1195 Japan

In recent years, neutrons have been studied for application in fields such as material analysis and boron neutron capture therapy. To create a compact shield for these facilities, a neutron shield concrete is developed. Verifying the homogeneity of the concrete is important to ensure adequate shielding performance. In this research, neutron radiography images of the concrete are taken using the Thermal Neutron Radiography Facility (TNRF) of the JRR-3 research reactor, and the transmission ratio of the thermal neutrons were estimated. The results showed that the transmission ratio of the concrete was almost the same at each depth. © 2014, Science Press. All rights reserved.

关键词：中子屏蔽同质性测试研究反应堆中子俘获屏蔽性能照相设备中子照相

Numerical modeling for the coupled thermo-mechanical processes and spalling phenomena in sp Pillar Stability Experiment (APSE)

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Journal of Rock Mechanics and Geotechnical Engineering 2013年第1期5卷 58-72页

作者： T.Koyama M.Chijimatsu H.Shimizu S.Nakama T.Fujita A.Kobayashi Y.Ohnishi Department of Urban Management Kyoto University Hazama Corporation Institute of Fluid Science Tohoku University Japan Atomic Energy Agency (jaea) Faculty of Environmental and Urban Engineering Kansai University Kyoto University

In this paper, the coupled thermo-mechanical （TM） processes in the AEspoe Pillar Stability Experiment （APSE） carried out by the Swedish Nuclear Fuel and Waste Management Company （SKB） were simulated using both continuum and discontinuum based numerical methods. Two-dimensional （2D） and three- dimensional （3D） finite element method （FEM） and 2D distinct element method （DEM） with particles were used. The main objective for the large scale in situ experiment is to investigate the yielding strength of crystalline rock and the formation of the excavation disturbed/damaged zone （EDZ） during excavation of two boreholes, pressurizing of one of the boreholes and heating. For the DEM simulations, the heat flow algorithm was newly introduced into the original code. The calculated stress, displacement and temperature distributions were compared with the ones obtained from in situ measurements and FEM simulations. A parametric study for initial microcracks was also performed to reproduce the spalling phenomena observed in the APSE.

关键词： Coupled thermo-mechanical (TM)processesAspoe Pillar Stability Experiment (APSE)Excavation disturbed/damaged zone (EDZ)Finite element method (FEM)Distinct element method (DEM)

Difference between low-volume and high-volume Andersen samplers in measuring atmospheric aerosols

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Particuology 2008年第3期6卷 218-222页

作者： Fengfu Fu Nobuo Shinohaya Mitsuo Ito Xueqin Xu Mincong Shen Liangjun Xu Key Lab of Analysis and Detecting Technology for Food Safety (Fuzhou University) of Ministry of Education Department of Chemistry Fuzhou University Fuzhou Fujian 350002 China Division of Environment and Radiation Sciences Japan Atomic Energy Agency (JAEA) Tokai-mura Naka-gun lbaraki 319-1195 Japan

The mass concentration and size distribution of aerosols in Tokaimura were investigated using a high-volume and a low-volume Andersen sampler. A difference was found using the two samplers： the concentration of total aerosols determined with the high-volume sampler is smaller than that of the low-volume sampler by 70-90% throughout the year. Compared to the high-volume sampler, low-volume sampler gave lower concentration for aerosols 〉7 μm, higher concentration for aerosols of 3.3-7.0 μm and 〈 1.1 μm, though similar results for aerosols of 1.1-3.3 μm. The low-volume sampler was found to have better separation efficiency and higher accuracy.

关键词： Aerosols Cascade impactor Andersen air sampler Atmospheric particles

Reactive and non-reactive transport modelling in partially water saturated argillaceous porous media around the ventilation experiment,Mont Terri

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Journal of Rock Mechanics and Geotechnical Engineering 2013年第1期5卷 44-57页

作者： Alexander Bond Steven Benbow James Wilson Alain Millard Shigeo Nakama Myles English Christopher McDermott Benoit Garitte Quintessa Ltd. Chadwick House Birchwood Park Warrington Cheshire WA3 6AE UK Commissariat à l'Energie Atomique Japan Atomic Energy Agency (jaea) University of Edinburgh Universidad Politécnica de Catalunya

At Mont Terri Underground Research Laboratory （URL） Switzerland, a specific experiment has been per- formed in a tunnel, in order to investigate the hydro-mechano-chemical （HMC） perturbations induced in the argillaceous formation by forced ventilation. This experiment has been selected in the international project DECOVALEX to be used for process model development and validation. The numerical simula- tion of the geochemical response to the ventilation experiment （VE） is the object of the present paper, focusing on the transport of chloride as a conservative species and sulphate as a reactive species. Uti- lising the validated hydro-mechanical （HM） results from earlier steps of the DECOVALEX task, reactive and non-reactive transport models, incorporating the current understanding of the geochemistry at the site, were successfully constructed for the whole experimental period. The associated parametric and process uncertainty analyses clearly demonstrate that the basic HM understanding must be sound. How- ever, to demonstrate this degree of robustness, the explicit inclusion of process representations of water desaturation, liquid vaporisation, species exclusion porosity, and redox processes, is required.

关键词： Reactive transportHydro-mechanical (HM) couplingNumerical modellingMont Terri Underground ResearchLaboratory (URL)Ventilation experiment (VE)ArgilliteChlorideSulphate

Evaluation study on properties of a macroporous silica-based CMPO extraction resin to be used forminor actinides separation from high level liquid waste

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Nuclear Science and Techniques 2011年第1期22卷 18-24页

作者： LIU Ruiqin WEI Yuezhou Daisuke Tozawa XU Yuanlai Shigekazu Usuda Hiromichi Yamazaki Keizo Ishii Yuichi Sano Yoshikazu Koma School of Nuclear Science and Engineering Shanghai Jiao Tong UniversityShanghai 200240China Cyclotron and Radioisotope Center Tohoku UniversityAoba 6-3Aramaki-Aoba-kuSendaiMiyagi980-8578Japan Japan Atomic Energy Agency (jaea) TokaiIbaraki319-1195Japan

Basic properties of a silica-based octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide (CMPO) extraction resin (CMPO/SiO2-P) was *** behavior for some rare earth elements (RE) which are constituents of high level liquid waste (HLLW) and the long-term stability of the extraction resin in nitric acid solution were *** CMPO extraction resin was significantly stable in 3 mol·L?1 HNO3 solution at ***,the RE(III) were efficiently separated from non-adsorptive fission product (FP) elements such as Sr(II) in a column experiment using a highly nitric acid *** separation behaviors of the elements are considered to result from the difference in their adsorption and elution selectivity based on the complex formation with *** was no strong dependency of RE(III) separation efficiency on feed solution flow *** from the perspectives of the acid-resistant behavior of CMPO extraction resin and the elution kinetics for the metal ions with the extraction resin,the CMPO extraction resin can be used in the modified MAREC process for HLLW partitioning.

关键词：萃取树脂高放废液锕系元素分离性能大孔硅提取基础选择性吸附

The New Neutron Source JSNS/J-PARC and Neutron Community in Japan

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The New Neutron Source JSNS/J-PARC and Neutron Community in ...

第三届散裂中子源多学科应用研讨会

作者： Yasuhiko Fujii Quantum Beam Science Directorate Japan Atomic Energy Agency (JAEA) Tokai Ibaraki 319-1195 Japan

Neutron scattering research in Japan started in early 1960’s when JAERI (the present jaea) built its JRR-2 reactor (10MW) in Tokai. It was soon followed by JRR-3 (10MW) in Tokai and Kyoto University’s *** reactor (5MW) in Kumatori. In addition to these research reactors, in mid 1960 Japan pioneered an accelerator-based neutron source at Tohoku University in Sendai and later in 1980 the first dedicated spallation neutron

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Estimation of the Initial Guess Spectrum for Estimation of Neutron Energy Spectra in the Vicinity of the Irradiation Facility of the BNCT

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Estimation of the Initial Guess Spectrum for Estimation of N...

作者： I.Urabe Y.Ogawa J.Saegusa K.Yamasaki School of Engineering Fukuyama University School of Science & Engineering Kinki University Dept.Radiation Protection NSRIJAEA

INTRODUCTION:Neutron energy spectra have been needed to know propagation characteristics of neutron doses around medical facilities utilizing nuclear reaction, Determination of neutron energy spectra which would usually be practiced by iteration methods using some measured data and response matrix representing sensitivity of detectors has been needed an initial guess spectrum for analysis of neutron energy spectra at places of interest around nuclear *** estimation of initial guess spectrum for using analysis of the data

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