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Title: Method and apparatus for extracting tritium and preparing radioactive waste for disposal

Abstract

Apparatus for heating an object such as a nuclear target bundle to release and recover hydrogen and contain the disposable residue for disposal. The apparatus comprises an inverted furnace, a sleeve/crucible assembly for holding and enclosing the bundle, conveying equipment for placing the sleeve onto the crucible and loading the bundle into the sleeve/crucible, a lift for raising the enclosed bundle into the furnace, and hydrogen recovery equipment including a trap and strippers, all housed in a containment having negative internal pressure. The crucible/sleeve assembly has an internal volume that is sufficient to enclose and hold the bundle before heating; the crucible's internal volume is sufficient by itself to hold and enclose the bundle's volume after heating. The crucible can then be covered and disposed of; the sleeve, on the other hand, can be reused.

Inventors:
 [1]
  1. Aiken, SC
Issue Date:
Research Org.:
Savannah River Site (SRS), Aiken, SC (United States)
OSTI Identifier:
869211
Patent Number(s):
5298196
Assignee:
United States of America as represented by United States (Washington, DC)
Patent Classifications (CPCs):
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01B - NON-METALLIC ELEMENTS
G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT
DOE Contract Number:  
AC09-89SR18035
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
method; apparatus; extracting; tritium; preparing; radioactive; waste; disposal; heating; nuclear; target; bundle; release; recover; hydrogen; contain; disposable; residue; comprises; inverted; furnace; sleeve; crucible; assembly; holding; enclosing; conveying; equipment; placing; loading; lift; raising; enclosed; recovery; including; trap; strippers; housed; containment; negative; internal; pressure; volume; sufficient; enclose; hold; covered; disposed; hand; reused; internal volume; apparatus comprises; radioactive waste; recover hydrogen; apparatus comprise; preparing radioactive; internal pressure; hydrogen recovery; /588/110/373/376/422/976/

Citation Formats

Heung, Leung K. Method and apparatus for extracting tritium and preparing radioactive waste for disposal. United States: N. p., 1994. Web.
Heung, Leung K. Method and apparatus for extracting tritium and preparing radioactive waste for disposal. United States.
Heung, Leung K. Sat . "Method and apparatus for extracting tritium and preparing radioactive waste for disposal". United States. https://www.osti.gov/servlets/purl/869211.
@article{osti_869211,
title = {Method and apparatus for extracting tritium and preparing radioactive waste for disposal},
author = {Heung, Leung K},
abstractNote = {Apparatus for heating an object such as a nuclear target bundle to release and recover hydrogen and contain the disposable residue for disposal. The apparatus comprises an inverted furnace, a sleeve/crucible assembly for holding and enclosing the bundle, conveying equipment for placing the sleeve onto the crucible and loading the bundle into the sleeve/crucible, a lift for raising the enclosed bundle into the furnace, and hydrogen recovery equipment including a trap and strippers, all housed in a containment having negative internal pressure. The crucible/sleeve assembly has an internal volume that is sufficient to enclose and hold the bundle before heating; the crucible's internal volume is sufficient by itself to hold and enclose the bundle's volume after heating. The crucible can then be covered and disposed of; the sleeve, on the other hand, can be reused.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Jan 01 00:00:00 EST 1994},
month = {Sat Jan 01 00:00:00 EST 1994}
}