Calculation and measurement of 235U and 238U fussion counter assembly detection efficiency

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Abstract

The detection efficiencies of two fission counter assemblies (235U and 238U) designed to measure the neutron flux at JET, have been determined for monoenergetic and radioactive neutron sources. The results are in good agreement with calculations using Monte Carlo neutron transport codes, when care is used in setting up the computer models. The mean difference between calculation and experiment is (7±7%).

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∗

On attachment to JET Joint Undertaking Abingdon, Oxon., England.

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