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KMID : 0364920050300020055
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Journal of Radiation Protection and Research
2005 Volume.30 No. 2 p.55 ~ p.60
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Evaluation of Neutron Flux Distributions of SMART-P IST Region for the Design of Ex-Core Detector
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Koo Bon-Seung
Kim Kyo-Yoon
Lee Jung-Chan
Jee Sung-Gyun
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Abstract
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The evaluation of neutron flux distribution was performed for the ex-core detector design of SMART-P. DORT and MCNP code were used for the calculation of energy-dependent neutron flux distribution at 100% full power condition. Two code results show that maximum thermal flux appears at the 1^{st} water region in IST region and agree within 10% difference. In addition, another evaluation was performed code with assumptions that cote was composed of fission source and control rod without fuel assemblies. These assumptions make neutron count rate to be minimized. As a results, maximum thermal flux showed 6.99{times}10^{-2}(n/cm^2-sec), when the strength of initial fission source was assumed as 1.0{times}10^8(n/sec). The main reason of these results is due to the thermalization of fast neutrons in the water region and thermal flux is proportional to 80% of total neutron flux. Therefore, optimization of filler material of detector guide tube, position of installation and axial length of detector segments is necessary for the design of ex-core detector to enhance the neutron count rate and above results could be used in ex-core detector design as a fluence requirement.
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KEYWORD
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SMART-P, Ex-core detector, IST(Internal Shielding Tank), DORT/MCNP, Neutron Flux
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