Mathematical modeling of heat transfer in Pu-238 ion exchange columns

Conference · Thu Jan 01 00:00:00 EST 1987

OSTI ID:5540359

Wehner, J A

The safety of increased Pu-238 loading on the larger ion exchange columns to be installed in the H-Canyon Frames was examined from the standpoint of the temperature increase of a fully-loaded column, following a flow interruption. A mathematical model incorporating self-heating and resin degradation was developed. Transient temperature profiles generated by this model indicate that the column loading limits may be safely scaled up in proportion to the column diameters. This model was also used to demonstrate that a short agitation period following an incomplete product elution step will appreciably decrease the maximum temperature rise of the resin bed.

• Research Organization: Savannah River Lab., Aiken, SC (USA)
• DOE Contract Number: AC09-76SR00001
• OSTI ID: 5540359
• Report Number(s): DP-MS-87-115; CONF-8710146-1-Vugraphs; ON: DE87014836
• Resource Relation: Conference: Plutonium/uranium recovery operations conference, Richland, WA, USA, 12 Oct 1987; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
LIQUID ION EXCHANGERS
HEAT TRANSFER
MATHEMATICAL MODELS
PLUTONIUM 238
RECOVERY
ADIABATIC PROCESSES
ELUTRIATION
NUCLEAR FUELS
RESINS
TEMPERATURE MEASUREMENT
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
ENERGY SOURCES
ENERGY TRANSFER
EVEN-EVEN NUCLEI
FUELS
HEAVY NUCLEI
ION EXCHANGE MATERIALS
ISOTOPES
MATERIALS
NUCLEI
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
PLUTONIUM ISOTOPES
POLYMERS
RADIOISOTOPES
REACTOR MATERIALS
SEPARATION PROCESSES
YEARS LIVING RADIOISOTOPES
NESDPS Office of Nuclear Energy Space and Defense Power Systems
050800* - Nuclear Fuels- Spent Fuels Reprocessing