TREATMENT OF FISSION PRODUCT WASTE
Abstract
A pyrogenic method of separating nuclear reactor waste solutions containing aluminum and fission products as buring petroleum coke in an underground retort, collecting the easily volatile gases resulting as the first fraction, he uminum chloride as the second fraction, permitting the coke bed to cool and ll contain all the longest lived radioactive fission products in greatly reduced volume.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4202762
- Patent Number(s):
- 2897049
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT
- NSA Number:
- NSA-14-003259
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
- Subject:
- WASTE DISPOSAL AND PROCESSING; ALUMINUM CHLORIDES; ALUMINUM NITRATES; ASHES; CHLORIDES; CHLORINE; COAL; COKE; COMBUSTION; FISSION PRODUCTS; GASES; NITRATES; PETROLEUM; RECOVERY; RESIDUES; SPUTTERING; VOLATILITY; WASTE DISPOSAL; WASTE SOLUTIONS
Citation Formats
Huff, J B. TREATMENT OF FISSION PRODUCT WASTE. United States: N. p., 1959.
Web.
Huff, J B. TREATMENT OF FISSION PRODUCT WASTE. United States.
Huff, J B. Tue .
"TREATMENT OF FISSION PRODUCT WASTE". United States.
@article{osti_4202762,
title = {TREATMENT OF FISSION PRODUCT WASTE},
author = {Huff, J B},
abstractNote = {A pyrogenic method of separating nuclear reactor waste solutions containing aluminum and fission products as buring petroleum coke in an underground retort, collecting the easily volatile gases resulting as the first fraction, he uminum chloride as the second fraction, permitting the coke bed to cool and ll contain all the longest lived radioactive fission products in greatly reduced volume.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {7}
}
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