혹시라도 미국 유학의 뜻이 있으신분들을 위해 실험보고서를 올립니다. 어떤식으로 작성하는가등등 자세히 참고하시면 도움이 될듯십네요.
2. Corrections and simplifications
4. Calculations and Results
5. Discussions and Sources of Error
This lab examines axial thermal flux distribution of the OSTR by the means of neutron activation analysis. This is done by irradiating 15 inch sections of bare and cadmium covered gold wire, and the activity of the radioactive product produced (Au-198) is measured under Au-198 - 412 keV peak using a Ge(Li) gamma ray detector and multi-channel analyzer. Since this activity is affected by the neutron flux in the point of irradiation and by the activation cross section of the target material, the neutron flux can be determined from the measurement of the activity in the wire, provided the activation cross section is known. Because Cadmium absorbs almost all neutrons with energy lower than 0.4 eV, but is nearly transparent to higher energy neutrons, the difference of the flux in the sections of wire with and without Cadmium cover gives the thermal flux.
Gamma intensity (Eu-152, Au-198)
Reactor Physics Constants ANL-5800, second edition