A5102752391- Nuclear Physics and Applications
- Radiation Detection and Scintillator Technologies
- Radioactive contamination and transfer
- Radiation Therapy and Dosimetry
- Nuclear reactor physics and engineering
- Radioactivity and Radon Measurements
- Nuclear and radioactivity studies
- Advanced X-ray and CT Imaging
- Advanced Chemical Sensor Technologies
- Gas Sensing Nanomaterials and Sensors
- Analytical Chemistry and Sensors
- Atomic and Subatomic Physics Research
- X-ray Spectroscopy and Fluorescence Analysis
- Graphite, nuclear technology, radiation studies
- Urban and spatial planning
- Chemical Synthesis and Characterization
- Particle Detector Development and Performance
- Radioactive Decay and Measurement Techniques
- Calibration and Measurement Techniques
- Radioactive element chemistry and processing
University of Colorado Boulder
2023
Hunan University of Science and Engineering
2023
Shihezi University
2023
Keio University
2023
Yancheng Teachers University
2023
Soochow University
2023
Charles Darwin University
2023
Jiangxi Normal University
2023
Lanzhou University
2023
Japan Atomic Energy Agency
2007-2020
Soil deposition density maps of gamma-ray emitting radioactive nuclides from the Fukushima Dai-ichi Nuclear Power Plant (NPP) accident were constructed on basis results large-scale soil sampling. In total 10,915 samples collected at 2168 locations. Gamma rays emitted measured by Ge detectors and analyzed using a reliable unified method. The determined radioactivity was corrected to that June 14, 2011 considering intrinsic decay constant each nuclide. Finally created for 134Cs, 137Cs, 131I,...
Abstract In 2011, after the Fukushima Dai-ichi Nuclear Power Plant accident, initial decrease in ambient dose equivalent rate ( dH *(10) dt −1 ), an alternative quantity to effective dose, was studied using monitoring data obtained from March 16, 2011. The normalized by 137 Cs activity per unit area (norm- ) analyze across sites with different deposition levels. norm- showed a rapid during first 60 days, followed slow and modeled two exponential functions. areas dominated paved surfaces...
The 8 and 27 keV monoenergetic neutron calibration fields have been developed by using (45)Sc(p, n)(45)Ti reaction. Protons from a 4-MV Pelletron accelerator are used to bombard thin scandium target evaporated onto platinum disc. proton energies finely adjusted the resonance generate neutrons applying high voltage assemblies. were measured time-of-flight method with lithium glass scintillation detector. fluences at point located 50 cm evaluated Bonner spheres. A long counter was placed 2.2 m...
Monoenergetic neutron calibration fields of 144, 565 keV and 5.0 MeV have been developed at the Facility Radiation Standards JAERI using a 4 MV Pelletron accelerator. The 7Li(p,n)7Be 2H(d,n)3He reactions are employed for production. energy was measured by time-of-flight method with liquid scintillation detector calculated MCNP-ANT code. A long counter is as monitor because flat response. set up where influence inscattered neutrons from devices their supporting materials point small possible....
AbstractThe neutron calibration fields using accelerators have been developed at the Facility of Radiation Standards (FRS) JAEA-Tokai for neutrons below 20 MeV and Takasaki Ion Accelerators Advanced Application (TIARA) JAEA-Takasaki those over MeV. At FRS, monoenergetic are generated by proton or deuteron beam from a 4 MV Van-de-Graaff (Pelletron) accelerator. Up until present, developments 8, 144, 250, 565 keV, 5.0 14.8 completed. As procedure development, measurement energy spectrum, peak...
In general, radioactivity measurements for volume samples are performed by the γ-ray spectrometry method with germanium detectors. method, peak efficiency curves must be obtained each kind of sample in advance. For reason, usually, many standard sources have been made which different shapes, densities, matrix compositions and so on. This paper describes about a simple determination combination Monte Carlo simulations single-point calibration using point source. enables us to determine...
Evaluation of the properties for quasi-monoenergetic neutron calibration fields high energies more than 20 MeV at TIARA is proceeding development field. Among needed as standard field, we report on measurement beam profile using an imaging plate with a polyethylene converter and estimation contribution scattered neutrons into irradiation field based pulse height distribution various off-beam positions measured organic liquid scintillation detector.
Development of three calibration fields for 45, 60 and 75 MeV neutrons has been in progress at Takasaki Ion Accelerators Advanced Radiation Application (TIARA) JAEA-Takasaki.Achievement the neutron requires establishment both measurement fluence its monitoring technique.In order to measure main energy peak especially a reference point on low condition, proton recoil counter telescope with high efficiency developed.The design relatively large components brought detection wide irradiation area...
In general, radioactivity measurements for volume samples are performed by the γ-ray spectrometry method with germanium detectors. method, peak efficiency curves must be obtained each kind of sample in advance. For reason, usually, many standard sources have been made which different shapes, densities, matrix compositions and so on. This paper describes about a simple determination combination Monte Carlo simulations single-point calibration using point source. enables us to determine...
AbstractA Monte Carlo code system, MCNP-ANT, has been developed to simulate the transport of charged particles (<4MeV) and neutron production in an accelerator target as well transport. The system consists a newly for particle production, existing code, MCNP-4B. available reactions are 2H(d,n)3He, 3H(d,n)4He, 3H(p,n)3He, 7Li(p,n)7Be 45Sc(p,n)45Ti main sources. calculated spectra by MCNP-ANT were compared with experimental ones typical monoenergetic fields.Keywords: calibration fieldMonte...
The Facility of Radiation Standards Japan Atomic Energy Research Institute has been equipped with concrete-moderated neutron calibration fields as simulated workplace fields. use an 241Am–Be source placed in the narrow space surrounded by concrete bricks, walls and floor. spectra fluence rates were measured Bonner multi-sphere spectrometer system (BMS), spherical recoil-proton proportional counters, a liquid scintillation counter (NE-213). results compared each other. reference values H*(10)...
Because of radioactive fallout resulting from the Fukushima Daiichi Nuclear Power Plant (NPP) accident, water discharge many outdoor swimming pools in was suspended out concern that radiocesium pool would flow into farmlands. The Japan Atomic Energy Agency has reviewed existing flocculation method for decontaminating and established a practical decontamination by demonstrating process at eight Fukushima. In this method, zeolite powder flocculant are used capturing present water. supernatant...
Spectrum changeable neutron calibration fields are planned to be established with an accelerator installed in Japan Atomic Energy Research Institute/Facility of Radiation Standards. The provided by bombarding a target surrounded moderator, charged particles from the accelerator. In fields, wide variety spectra is sufficient fluence rate for dosemeters. this study, necessity field was first discussed view relationship between readings existing dosemeters and true dose equivalents where were...
241Am-Be中性子線源を用いる中性子校正場は,中性子線量計の校正のために一般に広く用いられている。中性子線量計を適切に校正するためには,中性子校正場に関わる個々のパラメータを正確に決定する必要があるが,その中でも,校正点における中性子フルエンス率は重要なパラメータの一つである。中性子フルエンス率は線源中心から校正点までの距離と線源強度で決定されるが,それ以外に補正項を導入する必要がある。中性子は線源内で等方的に放出されるが,線源物質や線源を封じる壁材料との散乱は不可避であり,この効果によって中性子フルエンスの角度分布に変動が生じる。これを中性子放出の非等方性と呼び,その度合いを非等方係数FI(θ)で評価する。著者らは,(独)日本原子力研究開発機構 東海研究開発センター 原子力科学研究所...