Harmful biological effect in human body is one of important concerns in neutron infected places. In the other hand it is inevitable for someone to present in such environments. So, designing and manufacturing neutron dosimeter helps us to determine the best subject position toward the source for less received dose and an estimation of neutron destruction in body. International Commission of Radiological Protection, ICRP, introduce effective dose as a quantity that determines the amount of neutron destruction in whole-body. This quantity is computational and there is no way to measure it. The detector placed in neutron dosimeter only determines the neutron counts. In this research, besides the effective dose calculation, we specified a logical relationship between dosimeter counts and effective dose for 6 standard geometries.

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