SOLVENT EXTRACTION FLOWSHEET STUDIES WITH IRRADIATED FUEL FROM THE FAST FLUX TEST FACILITY.

D. E. Benker; J. E. Bigelow; W. D. Bond; E. B. Cagle; F. R. Chattin; L. J. King; F. G. Kitts; R. G. Ross; R. G. Stacy

SOLVENT EXTRACTION FLOWSHEET STUDIES WITH IRRADIATED FUEL FROM THE FAST FLUX TEST FACILITY.

D. E. Benker, J. E. Bigelow, W. D. Bond, E. B. Cagle, F. R. Chattin, L. J. King, F. G. Kitts, R. G. Ross, R. G. Stacy

Process Coordination

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

1 Scopus citations

Abstract

Two solvent extraction experiments were made in the Solvent Extraction Test Facility during 1983 using a small batch of low-burnup fuel from the Fast Flux Test Facility reactor as feed. No operational problems were noted in the operation of the extraction-scrubbing contactor, and low uranium and plutonium losses were measured. A noticeable improvement in the fission product decontamination factors was observed when the number of scrub stages was increased from six to eight. Two flowsheet options for making pure uranium and plutonium products were tested.

Original language	English
Title of host publication	Unknown Host Publication Title
Publisher	ANS
Pages	483-493
Number of pages	11
ISBN (Print)	0894481185
State	Published - 1984

Cite this

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title = "SOLVENT EXTRACTION FLOWSHEET STUDIES WITH IRRADIATED FUEL FROM THE FAST FLUX TEST FACILITY.",

abstract = "Two solvent extraction experiments were made in the Solvent Extraction Test Facility during 1983 using a small batch of low-burnup fuel from the Fast Flux Test Facility reactor as feed. No operational problems were noted in the operation of the extraction-scrubbing contactor, and low uranium and plutonium losses were measured. A noticeable improvement in the fission product decontamination factors was observed when the number of scrub stages was increased from six to eight. Two flowsheet options for making pure uranium and plutonium products were tested.",

author = "Benker, {D. E.} and Bigelow, {J. E.} and Bond, {W. D.} and Cagle, {E. B.} and Chattin, {F. R.} and King, {L. J.} and Kitts, {F. G.} and Ross, {R. G.} and Stacy, {R. G.}",

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AU - Benker, D. E.

AU - Bigelow, J. E.

AU - Bond, W. D.

AU - Cagle, E. B.

AU - Chattin, F. R.

AU - King, L. J.

AU - Kitts, F. G.

AU - Ross, R. G.

AU - Stacy, R. G.

PY - 1984

Y1 - 1984

N2 - Two solvent extraction experiments were made in the Solvent Extraction Test Facility during 1983 using a small batch of low-burnup fuel from the Fast Flux Test Facility reactor as feed. No operational problems were noted in the operation of the extraction-scrubbing contactor, and low uranium and plutonium losses were measured. A noticeable improvement in the fission product decontamination factors was observed when the number of scrub stages was increased from six to eight. Two flowsheet options for making pure uranium and plutonium products were tested.

AB - Two solvent extraction experiments were made in the Solvent Extraction Test Facility during 1983 using a small batch of low-burnup fuel from the Fast Flux Test Facility reactor as feed. No operational problems were noted in the operation of the extraction-scrubbing contactor, and low uranium and plutonium losses were measured. A noticeable improvement in the fission product decontamination factors was observed when the number of scrub stages was increased from six to eight. Two flowsheet options for making pure uranium and plutonium products were tested.

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M3 - Conference contribution

AN - SCOPUS:0021571152

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EP - 493

BT - Unknown Host Publication Title

PB - ANS

ER -

SOLVENT EXTRACTION FLOWSHEET STUDIES WITH IRRADIATED FUEL FROM THE FAST FLUX TEST FACILITY.

Abstract

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