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Title: DECLADDING OF CONSOLIDATED EDISON POWER REACTOR FUEL BY SULFEX AND DAREX PROCESSES: CYCLIC DISSOLUTION EXPERIMENTS

Technical Report ·
OSTI ID:4189020

Simulated Consolidated Edison reactor fuel pins (95.5% ere dissolved one- by-one according to the Sulfex and Darex flowsheets in Ni-o-nel and titanium vessels, respectively, 25 pins by each process. With boiling 5 M HNO/sub 3/--2 M HCl (Darex), dissolution of the cladding was complete in each cycle with uranium losses of 0.1--0.4%. Dissolution of the retical density) in boiling 13 M HNO/sub 3/--0.04 M NaF--0.04 M Al(NO/sub 3/)/sub 3/ was also complete in each case. No problems arose from passivation of stainless steel or crosscontamination of solutions. Two modifications of the Sulfex process were tested including decladding with 200% excess of 6 M H/sub 2/SO/sub 4/, and initiating the reaction with 6 M H/sub 2/SO/sub 4/ and diluting to 4 M sulfate shortly thereafter. Uranium losses to the decladding solution were generally between 0.2 and 0.5% irrespective of the technique, but were as high as 0.9% in the presence of a ThO/ sub 2/-- U/sub 3/O/sub 8/ heel. The uranium losses were directly related to the amount of heel present. In most cases the fuel pins were passive to boiling 6 M H/sub 2/SO/sub 4/ and reaction was initiated by contacting the pin with a piece of iron. Core dissolution was less efficient than in the Darex tests, presumably because of sulfate contamination. Under the flowsheet conditions only 98 to 99% of the core was dissolved in each cycle. (auth)

Research Organization:
Oak Ridge National Lab., Tenn.
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-14-009549
OSTI ID:
4189020
Report Number(s):
ORNL-2822
Resource Relation:
Other Information: Based on data obtained in corrosion studies at Battelle Memorial Institute under Subcontract 988 by C.L. Peterson, P.D. Miller, J.D. Jackson, and W.C. Baytos. Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English