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A survey of methods to immobilize tritium and carbon-14 arising from a nuclear fuel reprocessing plant

Abstract

This report reviews the literature on methods to separate and immobilize tritium ({sup 3}H) and carbon-14 ({sup 14}C) released from U0{sub 2} fuel in a nuclear fuel reprocessing plant. It was prepared as part of a broader review of fuel reprocessing waste management methods that might find future application in Canada. The calculated inventories of both {sup 3}H and {sup 14}C in used fuel are low; special measures to limit releases of these radionuclides from reprocessing plants are not currently in place, and may not be necessary in future. If required, however, several possible approaches to the concentration and immobilization of both radionuclides are available for development. Technology to control these radionuclides in reactor process streams is in general more highly developed than for reprocessing plant effluent, and some control methods may be adaptable to reprocessing applications.
Authors:
Publication Date:
Feb 01, 1991
Product Type:
Technical Report
Report Number:
AECL-10300
Reference Number:
SCA: 052001; 050800; PA: AIX-23:037139; SN: 92000726292
Resource Relation:
Other Information: PBD: Feb 1991
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CARBON 14; RADIOACTIVE WASTE MANAGEMENT; FUEL REPROCESSING PLANTS; TRITIUM; CANDU TYPE REACTORS; ISOTOPE SEPARATION; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; REPROCESSING; SPENT FUELS; 052001; 050800; WASTE PROCESSING; SPENT FUELS REPROCESSING
OSTI ID:
10139848
Research Organizations:
Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Nuclear Research Establishment
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE92627039; TRN: CA9200252037139
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
33 p.
Announcement Date:
Jul 05, 2005

Citation Formats

Taylor, P. A survey of methods to immobilize tritium and carbon-14 arising from a nuclear fuel reprocessing plant. Canada: N. p., 1991. Web.
Taylor, P. A survey of methods to immobilize tritium and carbon-14 arising from a nuclear fuel reprocessing plant. Canada.
Taylor, P. 1991. "A survey of methods to immobilize tritium and carbon-14 arising from a nuclear fuel reprocessing plant." Canada.
@misc{etde_10139848,
title = {A survey of methods to immobilize tritium and carbon-14 arising from a nuclear fuel reprocessing plant}
author = {Taylor, P}
abstractNote = {This report reviews the literature on methods to separate and immobilize tritium ({sup 3}H) and carbon-14 ({sup 14}C) released from U0{sub 2} fuel in a nuclear fuel reprocessing plant. It was prepared as part of a broader review of fuel reprocessing waste management methods that might find future application in Canada. The calculated inventories of both {sup 3}H and {sup 14}C in used fuel are low; special measures to limit releases of these radionuclides from reprocessing plants are not currently in place, and may not be necessary in future. If required, however, several possible approaches to the concentration and immobilization of both radionuclides are available for development. Technology to control these radionuclides in reactor process streams is in general more highly developed than for reprocessing plant effluent, and some control methods may be adaptable to reprocessing applications.}
place = {Canada}
year = {1991}
month = {Feb}
}