| Project/Area Number |
17560745
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| Research Category |
Grant-in-Aid for Scientific Research (C)
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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 | Kyoto University |
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Principal Investigator |
PYEON Cheol Ho Kyoto University, Research Reactor Institute, Assistant Professor (50362413)
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| Co-Investigator(Kenkyū-buntansha) |
MISAWA Tsuyoshi Kyoto University, Research Reactor Institute, Associate Professor (70219616)
UNESAKI Hironobu Kyoto University, Research Reactor Institute, Associate Professor (40213467)
SHIROYA Seiji Kyoto University, Research Reactor Institute, Professor (80027474)
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| Project Period (FY) |
2005 – 2007
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| Project Status |
Completed (Fiscal Year 2007)
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| Budget Amount *help |
¥2,290,000 (Direct Cost: ¥2,200,000、Indirect Cost: ¥90,000)
Fiscal Year 2007: ¥390,000 (Direct Cost: ¥300,000、Indirect Cost: ¥90,000)
Fiscal Year 2006: ¥500,000 (Direct Cost: ¥500,000)
Fiscal Year 2005: ¥1,400,000 (Direct Cost: ¥1,400,000)
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| Keywords | Accelerator-Driven / Subcritical Reactor / KUCA Experiments / Neutronic Characteristics / Foil Activation Method / 放射化箔 |
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| Research Abstract |
The following conclusions revealed in the basic experiments on Accelerator-Driven Subcritical Reactor (ADSR) conducted in the Kyoto University Critical Assembly (KUCA) : 1) It was confirmed that the effect on and the validity of the neutron guide, which was constituted in several neutron shielding materials and a beam duct, were found in the polyethylene region by conducting the foil activation experiments ; 2) it was obtained with the neutron spectrum information on the optimal irradiation foils for 14 MeV neutrons by conducting the experimental and numerical analyses of the reaction rates and the unfolding method ; 3) it was confirmed in an optimal experimental methodology of neutron spectrum analyses in around 100 MeV neutrons generated from the Fixed Field Alternating Gradient (FFAG) accelerator with tungsten (W) target ; 4) it was found in a suitable method of Monte Carlo MCNPX and the unfolding method for obtaining the neutron spectrum information. As the future works, considering an introduction of FFAG accelerator, 1) it is expected that optimal nuclear design calculations using MCNPX could be executed in the kinetic analyses of reactivity and reaction rates with around 150 MeV protons ; 2) it is requisite to investigate the precision of the Monte Carlo calculations for establishment of measurement techniques around the neutronic characteristics in the target and the core regions, after the introduction the FFAG accelerator.
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