An overview of measurement methods for special nuclear material in spent nuclear fuel [electronic resource]
Summary results from a survey of nondestructive assay measurement methods applicable to the measurement of the special nuclear material content of spent nuclear fuel are described. The role of nuclear materials measurements in the domestic and international safeguarding of spent nuclear fuel in the...
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| Online Access: |
Online Access |
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| Corporate Authors: | , |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Oak Ridge, Tenn. : Oak Ridge, Tenn. :
Oak Ridge Gaseous Diffusion Plant ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1989.
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| Subjects: |
| Summary: | Summary results from a survey of nondestructive assay measurement methods applicable to the measurement of the special nuclear material content of spent nuclear fuel are described. The role of nuclear materials measurements in the domestic and international safeguarding of spent nuclear fuel in the United States' federal waste management system has yet to be determined. An understanding of the characteristics and capabilities of the potentially applicable measurement systems should provide valuable information to the developers of the safeguards approaches for the monitored retrievable storage and final disposal systems. The discussion focuses on the general characteristics of the identified direct and indirect measurement methods. 3 refs., 1 tab. |
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| Item Description: | Published through SciTech Connect. 07/01/1989. "k/itp-252" " conf-890736-41" "DE89015496" 30. annual meeting of the Institute of Nuclear Materials Management, Orlando, FL, USA, 9-12 Jul 1989. Moran, B.W.; Reich, W.J. |
| Physical Description: | Pages: 6 : digital, PDF file. |