한국방사성폐기물학회:학술대회논문집 (Proceedings of the Korean Radioactive Waste Society Conference)
- 한국방사성폐기물학회 2005년도 춘계 학술대회
- /
- Pages.344-349
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- 2005
Neutron Count Rate Measurement of $UO_2$ powder by Neutron Source
-
Kang Hee-Young
(Korea Atomic Energy Research Institute)
;
-
Koo Gil-Mo
(Korea Atomic Energy Research Institute)
;
-
Ha Jang-Ho
(Korea Atomic Energy Research Institute)
;
-
Kim Ho-Dong
(Korea Atomic Energy Research Institute)
;
- Yang Myung-Seung (Korea Atomic Energy Research Institute)
- 발행 : 2005.06.01
초록
Neutron count rate measurements to assay fissile content of uranium powder have been carried out in a neutron counter. The induced fission neutrons by Cf-252 neutron source are counted as the variation of fissile material in fuel material. The measured counts are compared with equivalent results obtained from calculation. It shows that the measured neutron counts versus quantity of
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