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논문 기본 정보
- 자료유형
- 학술대회자료
- 저자정보
- 발행연도
- 2005.1
- 수록면
- 344 - 349 (6page)
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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 $UO_2$ powder enrichment agreed reasonably well with the calculated values.
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