Published January 13, 2000
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WASTE HANDLING BUILDING SHIELD WALL ANALYSIS
Description
The scope of this analysis is to estimate the shielding wall, ceiling or equivalent door thicknesses that will be required in the Waste Handling Building to maintain the radiation doses to personnel within acceptable limits. The shielding thickness calculated is the minimum required to meet administrative limits, and not necessarily what will be recommended for the final design. The preliminary evaluations will identify the areas which have the greatest impact on mechanical and facility design concepts. The objective is to provide the design teams with the necessary information to assure an efficient and effective design
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00861910; PURL: https://www.osti.gov/servlets/purl/861910-jBh8oO/Files
37046800.pdf
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 94 p.
- Report number
- BCBD--00000-01717-0200-00011
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 37046800
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- DESIGN; DOORS; MATERIALS HANDLING; RADIATION DOSES; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTES; SHIELDING; SHIELDS; THICKNESS
- Descriptors DEC
- DIMENSIONS; DOSES; MATERIALS; NUCLEAR FACILITIES; OPENINGS; RADIOACTIVE MATERIALS; WASTES
Optional Information
- Funding organization
- US Department of Energy (United States)
- Secondary number(s)
- MOL--19990111.0156; DC-No--24289