Fractional Release Behavior of Volatile and Semivolatile Fission Products During a Voloxidation and OREOX Treatment of Spent PWR Fuel

Abstract Quantitative analysis of the fission gas release characteristics during the voloxidation and oxidation and reduction of oxide fuel (OREOX) processes of spent pressurized water reactor (PWR) fuel was carried out by spent PWR fuel in a hot cell of the DUPIC Fuel Development Facility. The release characteristics of 85Kr and 14C fission gases during voloxidation process at 500°C are closely linked to the degree of conversion efficiency of UO2 to U3O8 powder, and it can be interpreted that the release from grain boundary would be dominated during this step. Volatile fission gases of 14C and 85Kr were released to near completion during the OREOX process. Both the 14C and 85Kr have similar release characteristics under the voloxidation and OREOX process conditions. A higher burnup spent fuel showed a higher release fraction than that of a low burnup fuel during the voloxidation step. It was also observed that the release fraction of semivolatile Cs was ~16% during a reduction at 1000°C of the oxidized powder, but over 90% during the voloxidation at 1250°C.

[1]  D. R. Johnson,et al.  Measurement of radioactive gaseous effluents from voloxidation and dissolution of spent nuclear fuel , 1978 .

[2]  P. Perrot,et al.  Evaluation of the Cs–Mo–I–O and Cs–U–I–O diagrams and determination of iodine and oxygen partial pressure in spent nuclear fuel rods , 2005 .

[3]  Yongsoo Kim,et al.  Theoretical analysis of two-stage fission gas release processes: grain lattice and grain boundary diffusion , 2004 .

[4]  A. Sasahara,et al.  Fission product release in high-burn-up UO2 oxidized to U3O8 , 2006 .

[5]  D. Papaioannou,et al.  Phase characterisation of simulated high burn-up UO2 fuel , 1998 .

[6]  R. Konings,et al.  The release of fission products from degraded UO2 fuel: Thermochemical aspects , 1993 .

[7]  W. Ko,et al.  Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors—IV: DUPIC Fuel Cycle Cost , 2001 .

[8]  S. R. Manning,et al.  Behavior of iodine, methyl iodide, cesium oxide, and cesium iodide in steam and argon , 1976 .

[9]  Myung Seung Yang,et al.  THE STATUS AND PROSPECT OF DUPIC FUEL TECHNOLOGY , 2006 .

[10]  M. S. Yang,et al.  Conceptual study on the DUPIC fuel manufacturing technology , 1993 .

[11]  K. Yamazaki,et al.  Study on voloxidation process for tritium control in reprocessing , 1992 .

[12]  G. C. Jain,et al.  Densification behaviour of UO2 in six different atmospheres , 2002 .

[13]  M. Mogensen,et al.  Observations on the release of cesium from UO2 fuel , 1996 .

[14]  J. Evans Post-irradiation fission gas release from high burn-up UO2 fuel annealed under oxidising conditions , 1997 .

[15]  B. Westphal,et al.  Fission Product Removal from Spent Oxide Fuel by Head-End Processing , 2005 .

[16]  J. S. Lee,et al.  Research and development program of KAERI for DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors) , 1993 .

[17]  Myung Seung Yang,et al.  Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors—I: DUPIC Fuel Fabrication Cost , 2001 .