Measurement and analysis of neutron emission rate for irradiated BWR fuel.

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概要

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• Neutron emission rates for irradiated BWR fuel bundles were measured and compared with calculated results. The axial thermal neutron flux distributions outside the channel box of the fuel bundles were measured by means of Au-foil activation technique and con-verted into neutron emission rate using the calculated conversion factors. The decay of neutron emission rate was also measured and the contribution of <SUP>242</SUP>Cm to neutron emission was evaluated from the results. Calculations were carried out using the lattice cell burnup calculation code and two-dimensional diffusion code. Spontaneous fission and <SUP>18</SUP>O(α, <I>n</I>)<SUP>21</SUP>Ne reaction were considered as the neutron-producing processes, and eight transuranium nuclides essential to neutron emission were taken into account. For the magnitude of neutron emis-sion rate, calculations showed reasonable agreements with measurements in view of the accuracy of nuclear data used. However, some systematic discrepancies between calcula-tions and measurements were found and these discrepancies are considered to have resulted from the biases in the calculated exposure values.

• 一般社団法人 日本原子力学会の論文

著者

• UEDA Makoto

  NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co., Ltd.

• YOKOYAMA Tsutomu

  NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co., Ltd.

• KUROSAWA Fumio

  NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co., Ltd.

• ENOMOTO Toshiaki

  The Tokyo Electric Power Co., Inc.

関連論文

• Method of measuring boron-10 depletion in control blade.
• Measurement and analysis of neutron emission rate for irradiated BWR fuel.

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