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Prediction analysis of dose equivalent responses of neutron dosemeters used at a MOX fuel facility

Tsujimura, Norio  ; Yoshida, Tadayoshi ; Takada, Chie 

To predict how accurately neutron dosemeters can measure the neutron dose equivalent (rate) in a MOX fuel fabrication facility work environments, the dose equivalent responses of neutron dosemeters were calculated by the spectral folding method. The dosemeters selected included two types of personal dosemeters, namely a thermoluminescent albedo neutron dosemeter and an electronic neutron dosemeter, three moderator-based neutron survey meters, and one special instrument called an $$H$$$$_{rm p}$$(10) monitor. The calculations revealed the energy dependences of the responses expected within the entire range of neutron spectral variations observed in neutron fields at workplaces.

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Category:Environmental Sciences

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