Bibliographic Details
| Title: |
Thermal aspects in the design of an HTGR fuel reprocessing plant |
| Authors: |
Park, U.S. |
| Source: |
87. AICHE national meeting, Boston, MA, USA, 19 Aug 1979 |
| Publisher Information: |
General Atomic Company |
| Publication Year: |
1979 |
| Collection: |
University of North Texas: UNT Digital Library |
| Subject Terms: |
Fuels, Reprocessing, Temperature Effects, Energy Sources, Reactors, Graphite Moderated Reactors, 11 Nuclear Fuel Cycle And Fuel Materials, Nuclear Facilities, Spent Fuels, Fuel Reprocessing Plants, Reactor Materials, Nuclear Fuels, Gas Cooled Reactors, Separation Processes 050800* -- Nuclear Fuels-- Spent Fuels Reprocessing, Thorex Process, Htgr Type Reactors, Design |
| Description: |
HTGR graphite-based spent fuel has been thermally analyzed to provide data for a reprocessing design. Steps include crushing, burning in fluidized beds, size classification, dissolution, and solvent extraction. The principal problem is that the bunkers holding feed and product between steps need sizing for decay heat. Constraints have been set for different modes of cooling. However, criticality may prove stricter. Adverse effects of solvent degradation products in the Acid--Thorex process, mainly dibutyl phosphate (DBP), are reduced by using a partition flowsheet and by adding fluoride ions to the 1BX and 1CX columns. |
| Document Type: |
article in journal/newspaper |
| File Description: |
19 pages; Text |
| Language: |
English |
| Relation: |
osti: 5912681; https://digital.library.unt.edu/ark:/67531/metadc1097208/; ark: ark:/67531/metadc1097208 |
| Availability: |
https://digital.library.unt.edu/ark:/67531/metadc1097208/ |
| Accession Number: |
edsbas.A4B34329 |
| Database: |
BASE |