Design of a variable-flow-rate, single-pass leaching system
Description
We have designed leaching systems for experiments on several kinds of solids, including glassy debris from underground nuclear explosions at Nevada Test Site (puddle glass), refractory compositions for retention of radioactive nuclear reactor waste, and spent reactor fuel. The system used on puddle glass has a continuously variable flow rate from 13 to 460 cm3/d, a temperature range from 25 to 750C, operating capacity for up to 20 simultaneous experiments, and one-pass operation with continuous exposure of samples to fresh solution. Results obtained on puddle glass are in qualitative agreement with those on silicate glasses designed for isolation of nuclear reactor waste
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 24 p.
- Report number
- UCRL--52785
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11518526
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S61: RADIATION PROTECTION AND DOSIMETRY; S42: ENGINEERING;
- Descriptors DEI
- FLOW RATE; GLASS; GROUND WATER; LEACHING; NUCLEAR EXPLOSIONS; RADIOACTIVE WASTES; REFRACTORIES; SOLIDS; SPECIFICATIONS; SPENT FUELS; TESTING; UNDERGROUND EXPLOSIONS
- Descriptors DEC
- DISSOLUTION; ENERGY SOURCES; EXPLOSIONS; FUELS; HYDROGEN COMPOUNDS; NUCLEAR FUELS; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SEPARATION PROCESSES; WASTES; WATER