| Project/Area Number |
14380239
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| Research Category |
Grant-in-Aid for Scientific Research (B)
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| Allocation Type | Single-year Grants |
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| Section | 一般 |
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| Research Field |
Nuclear engineering
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| Research Institution | Musashi Institute of Technology |
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Principal Investigator |
MATSUMOTO Tetsuo Musashi Institute of Technology, Engineering, Professor, 工学部, 教授 (00139411)
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| Co-Investigator(Kenkyū-buntansha) |
MOCHIKI Koichi Musashi Institute of Technology, Engineering, Professor, 工学部, 教授 (80107549)
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| Project Period (FY) |
2002 – 2004
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| Project Status |
Completed (Fiscal Year 2004)
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| Budget Amount *help |
¥5,300,000 (Direct Cost: ¥5,300,000)
Fiscal Year 2004: ¥2,200,000 (Direct Cost: ¥2,200,000)
Fiscal Year 2003: ¥2,100,000 (Direct Cost: ¥2,100,000)
Fiscal Year 2002: ¥1,000,000 (Direct Cost: ¥1,000,000)
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| Keywords | Low intensity radiography / 252Cf neutron source / D-D, D-T neutron tubes / Nondestructive technique / Neutron beam design / Monte Carlo simulation / Visual technique / Neutron image tube / DD、DT加速管 / フォトカウンテングシステム / CCDカメラ / 解像度・分解能 / 中性子線源(^<241>Am-Be、^<252>Cf) / モンテカルロ計算コードMCNP / 中性子照射場 / γ / n比 |
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| Research Abstract |
Transportable neutron radiography(NRG) system was examined with view to both generating neutron beams and developing a real-time image processing system. First, neutron beams with different spectra were designed by Monte Carlo calculation(MCNP) for a ^<252>Cf radioisotope when optimizing combination of moderator, neutron filter and shielding materials. Calculation values of thermal neutron flux (10^3 ncm^<-2>s^<-1>) with gamma-ray dose rate (0.5 mSvh^<-1>) were verified by the experiment at the irradiation port of 30 cm from the source. Next, a high intensity imaging intensifier (I.I) camera and a signal processing system were developed and were examined by X-rays. The signal processing system has three frame accumulation memories for normal, binary-converted and center-of-gravity frames for real-time image processing. The system was examined by using ^<252>Cf neutron source. Finally, a D-D neutron tube is suggested as better neutron source of a transportable module than ^<252>Cf neutron source for application to low intensity radiography.
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