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)