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Title: Method for treating a nuclear process off-gas stream

Abstract

Disclosed is a method for selectively removing and recovering the noble gas and other gaseous components typically emitted during nuclear process operations. The method is adaptable and useful for treating dissolver off-gas effluents released during reprocessing of spent nuclear fuels whereby to permit radioactive contaminant recovery prior to releasing the remaining off-gases to the atmosphere. Briefly, the method sequentially comprises treating the off-gas stream to preliminarily remove NOx, hydrogen and carbon-containing organic compounds, and semivolatile fission product metal oxide components therefrom; adsorbing iodine components on silver-exchanged mordenite; removing water vapor carried by said stream by means of a molecular sieve; selectively removing the carbon dioxide components of said off-gas stream by means of a molecular sieve; selectively removing xenon in gas phase by passing said stream through a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from oxygen by means of a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from the bulk nitrogen stream using a molecular sieve comprising silver-exchanged mordenite cooled to about -140.degree. to -160.degree. C.; concentrating the desorbed krypton upon a molecular sieve comprising silver-exchange mordenite cooled to about -140.degree. to -160.degree. C.; and further cryogenically concentrating, and the recovering for storage, the desorbed krypton.

Inventors:
;
Issue Date:
Research Org.:
Science Applications Inc., La Jolla, CA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
864992
Patent Number(s):
4447353
Application Number:
06/384,307
Assignee:
The United States of America as represented by the United States Department of Energy (Washington, DC)
Patent Classifications (CPCs):
G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT
DOE Contract Number:  
AC09-77SR00979
Resource Type:
Patent
Resource Relation:
Patent File Date: 1982 Jun 02
Country of Publication:
United States
Language:
English
Subject:
method; treating; nuclear; process; off-gas; stream; disclosed; selectively; removing; recovering; noble; gas; gaseous; components; typically; emitted; operations; adaptable; useful; dissolver; effluents; released; reprocessing; spent; fuels; whereby; permit; radioactive; contaminant; recovery; prior; releasing; remaining; off-gases; atmosphere; briefly; sequentially; comprises; preliminarily; remove; hydrogen; carbon-containing; organic; compounds; semivolatile; fission; product; metal; oxide; therefrom; adsorbing; iodine; silver-exchanged; mordenite; water; vapor; carried; means; molecular; sieve; carbon; dioxide; xenon; phase; passing; comprising; separating; krypton; oxygen; bulk; nitrogen; cooled; -140; degree; -160; concentrating; desorbed; silver-exchange; cryogenically; storage; selectively separating; gaseous components; containing organic; nuclear fuels; selectively removing; fission product; organic compound; gas phase; molecular sieve; water vapor; organic compounds; carbon dioxide; nuclear fuel; metal oxide; gas stream; spent nuclear; noble gas; off-gas stream; removing water; product metal; process operations; comprises treating; sequentially comprises; nuclear process; comprising silver; method sequentially; oxide component; volatile fission; gaseous component; gas effluent; radioactive contaminant; /423/976/

Citation Formats

Pence, Dallas T., and Chou, Chun-Chao. Method for treating a nuclear process off-gas stream. United States: N. p., 1984. Web.
Pence, Dallas T., & Chou, Chun-Chao. Method for treating a nuclear process off-gas stream. United States.
Pence, Dallas T., and Chou, Chun-Chao. Sun . "Method for treating a nuclear process off-gas stream". United States. https://www.osti.gov/servlets/purl/864992.
@article{osti_864992,
title = {Method for treating a nuclear process off-gas stream},
author = {Pence, Dallas T. and Chou, Chun-Chao},
abstractNote = {Disclosed is a method for selectively removing and recovering the noble gas and other gaseous components typically emitted during nuclear process operations. The method is adaptable and useful for treating dissolver off-gas effluents released during reprocessing of spent nuclear fuels whereby to permit radioactive contaminant recovery prior to releasing the remaining off-gases to the atmosphere. Briefly, the method sequentially comprises treating the off-gas stream to preliminarily remove NOx, hydrogen and carbon-containing organic compounds, and semivolatile fission product metal oxide components therefrom; adsorbing iodine components on silver-exchanged mordenite; removing water vapor carried by said stream by means of a molecular sieve; selectively removing the carbon dioxide components of said off-gas stream by means of a molecular sieve; selectively removing xenon in gas phase by passing said stream through a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from oxygen by means of a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from the bulk nitrogen stream using a molecular sieve comprising silver-exchanged mordenite cooled to about -140.degree. to -160.degree. C.; concentrating the desorbed krypton upon a molecular sieve comprising silver-exchange mordenite cooled to about -140.degree. to -160.degree. C.; and further cryogenically concentrating, and the recovering for storage, the desorbed krypton.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1984},
month = {1}
}