Published October 30, 1998
| Version v1
Report
MC and A in a Radiochemical Plant
Description
MC and A in reprocessing plant in the United States is based on solution measurements of the dissolved fuel assemblies, periodic inventories, and solution measurement of product and waste streams.
Additional details
Publishing Information
- Imprint Pagination
- [vp]
- Report number
- WSRC-MS--98-00752
Conference
- Title
- Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants
- Dates
- 2-6 Nov 1998
- Place
- Obninsk (Russian Federation)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 30058582
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- MATERIAL BALANCE; MEETINGS; NUCLEAR MATERIALS MANAGEMENT; SAVANNAH RIVER PLANT
- Descriptors DEC
- MANAGEMENT; NATIONAL ORGANIZATIONS; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Contract/Grant/Project number
- Contract AC09-96SR18500
- Funding organization
- DOE, Department of Energy (United States)