Solvent performance in THTR nuclear fuel reprocessing. I. Calculation of doses received by TBP-n-paraffin extractant in reprocessing THTR fuels applying a Thorex flowsheet
The radiolytic load of the 30 vol % tributylphosphate-n-paraffin extractant to be used in the Juelich Pilot Plant for Thorium Element Reprocessing facility for reprocessing thorium high-temperature reactor (THTR) fuel elements with high burnup values (85,000 MWd/MT of heavy-metal atoms) was calculated. At a radioactivity level of approx. 2000 Ci/l, the effective beta-particle power density of the feed solution ranges up to 15 W . l/sup -1/. Most of the energy absorbed by the extractant is due to beta radiation (99%). About 1% originates from gamma radiation; contributions from alpha-particle emitters are negligible. The calculations consider the geometric parameters of the applied mixer-settler and the operational parameters of the flowsheet. The highest exposure expected will be approx. 0.2 Wh . l/sup -1/ when reprocessing fuel with 85,000 MWd/MT burnup after a cooling time of 100 days. For an easier comparison of the calculated value with other reported values, a coefficient is introduced describing the specific exposure of the extractant in terms of energy absorption per hour of passing through the contactor at a power density of l W . l/sup -1/ in the feed solution. This coefficient is independent of such individual flowsheet conditions as heavy-metal concentration or power density in the feed solution. Comparison of calculated data with other reported data for THOREX and PUREX reprocessing runs exhibits only about a four-fold specific load of the extractant in case of reprocessing high-burned-up THTR fuel with respect to low-enriched low-burned-up light water reactor fuel. This underproportional increase is due to the specific fission-product spectrum of the investigated THTR fuel arising in the course of its reactor residence time.
- Research Organization:
- Kernforschungsanlage, Juelich, Ger.
- OSTI ID:
- 7089535
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 34:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ALKANES
BUTYL PHOSPHATES
DOSES
ENERGY SOURCES
ESTERS
FUEL ELEMENTS
FUEL REPROCESSING PLANTS
FUELS
HYDROCARBONS
NUCLEAR FACILITIES
NUCLEAR FUELS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
ORGANIC SOLVENTS
OTHER ORGANIC COMPOUNDS
PARAFFIN
PERFORMANCE
PHOSPHORIC ACID ESTERS
RADIATION DOSES
REACTOR COMPONENTS
REACTOR MATERIALS
REPROCESSING
SEPARATION PROCESSES
SOLVENTS
SPENT FUEL ELEMENTS
SPENT FUELS
TBP
THOREX PROCESS
WAXES