円環ダクト漏洩放射線の測定と計算

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Radiation streaming through a straight annular duct in an unsymmetrical configuration and an annular duct with one bend were measured by activation detector and thermoluminescence detector. Experimental results were obtained in terms of reaction rate and dose rate. Experimental errors were less than 29% for reaction rate and less than 19% for dose rate. Thermal and epithermal neutron fluxes were also obtained from the measured reaction rates under the assumption of 1/E spectrum in the intermediate energy region. On the former configuration, fast neutron flux distribution in duct was mainly determined by the component penetrating through water shield from the core. On the other hand, thermal and epithermal neutron flux distributions were mainly determined by streaming component. On the latter configuration, the bent part had appreciable shielding effect for fast neutron and gamma-ray, though this effect was small for lower energy neutron. Calculation was made for the former unsymmetrical configuration with the aid of PALLAS-2D two dimensional transport code in which two steps of calculation were taken, that is, first, the calculation for angular flux distribution in water, secondly, the calculation for the duct with symmetrical boundary condition obtained from the first step's calculation. Although there was a discrepancy on attenuation rate between calculation and measurement, agreement was quite fair for the fast neutron flux distribution along the duct axis. In the case of lower energy neutron flux distribution along the duct axis, calculation overestimated within a factor of 3, though fairly good agreement was obtained with respect to the attenuation rate. It was considered that these discrepancies were mainly arising from the insufficient boundary condition taken in the second step's calculation.
独立行政法人海上技術安全研究所の論文
1979-11-30

円環ダクト漏洩放射線の測定と計算

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