LMFBR fuel

Plutonium breeder LMFBR fuels, 6, 926 Plutonium carbide nuclear fuels, 6, 928 Plutonium complexes, 3,1131-1215 cupferron, 2, 510 Plutonium(III) complexes... 

Granziera, R., and M. S. Kazimi, 1980, A Two-Dimensional Two-Fluid Model for Sodium Boiling in LMFBR Fuel Assemblies, Energy Laboratory Rep. No. MIT-EL-80-011, Massachusetts Institute of Technology, Cambridge, MA. (4)... 

Figure 10.94 Calculated ratios of amounts of Te Cs, l Cs and Te I in the gas phase as a function of oxygen potential within the fiiel-clad gap of a LMFBR fuel pin assuming (a) no fuel takes part in the reaction and (b) fuel is included in the reaction (Ball et at. 1989).

Proceedings of the IAEA Meeting on LMFBR Fuel Reprocessing, Leningrad, 1976 , translated by ERDA. 

Knighton, J.B. Baldwin, C.E. Pyrochemical Coprocessing of Uranium Dioxide-Plutonium Dioxide LMFBR Fuel by the Salt Transport Method, Rocky Flats Report RFP-2887, CONF-790415-29 (1979). 

Plants in the UK, USSR and France are now reprocessing irradiated UO2/PUO2 fuels and LMFBR fuel reprocessing has been the subject of international conferences. " The plant at Cap la Hague, France, employs a 30% TBP solution and no U/Pu separation is undertaken, so that a mixed U/Pu product is obtained. Fluoride is added to the process feed to complex zirconium and suppress its extraction." The Dounreay plant in the UK employs a 20% TBP/OK solution and uses sulfuric acid to effect the U/Pu separation. TBP poorly extracts Pu or U from sulfuric acid solutions, but in mixed HNO3/H2SO4 the equilibria shown in equations (206) and (207) must be considered. The equilibrium constants for these reactions, Kj, and K i, are given... 

J. Leary, H. Kittel, eds.. Advanced LMFBR Fuels, Proc. Int. Topical Meeting, October 10-13, 1977, Tucson, AZ American Nuclear Society, La Grange, IL, 1977. 

Pyrochemical Coprocessing of Uranium Dioxide-Plutonium Dioxide LMFBR Fuel by the Salt Transport Method... 

The present work at Rocky Flats is an extension of the Argonne work and is directed to development of a proliferation resistant pyrochemical process for LMFBR fuels. This article describes a conceptual pyrochemical process and preliminary engineering concepts for coprocessing uranium and plutonium in spent LMFBR core-axial blanket and radial blanket fuels using the Salt Transport Process. 

Criteria used to develop the conceptual pyrochemical process for coprocessing uranium and plutonium from spent LMFBR fuel include the following ... 

Changes in fuel assembly size will increase or decrease plant throughput. Processing more than one fuel assembly per batch will require an increase in vessel size. Additional capacity also can be achieved by establishing parallel operations. The single fuel assembly per batch operation can process up to 200 tons per year of mixed oxide LMFBR fuel or up to eight fuel assemblies per day. 

Aqueous Processing of LMFBR Fuels, Technical Assessment and Experimental Program" ORNL-4436, June 1970. 

The second approach, which represents a departure from previous Pur ex partitioning, provides for the quantitative reduction of Pu to Pu3 with HAN and N Hlf (as the holding reductant) prior to the introduction of the U- and Pu-containing feed into a second cycle extraction column (Fig. 2). This method was proposed for both the EXXON reprocessing plant in Tennessee (10) and the ORNL Reprocessing Facility for LMFBR fuel (11). HAN will continue to be an attractive reductant because, not only is the introduction of metallic cations avoided, but HAN is decomposed safely by heating at temperatures above 60°C, which simplifies the reoxidation of Pu to Pu prior to subsequent extraction cycles. 

Baumgartner, F., Ochsenfeld, W., and Schmieder, H., "Development Work on Reprocessing of Oxidic LMFBR Fuel by the Purex Process," Paper presented at 82nd AIChE Mtg., Atlantic City, N.J., 1976. 

Tsujino, T. Advisory Group Meeting on Reprocessing of LMFBR fuels (Leningrad, USSR, 1976). 

Richardson, G. L. The Effect of High Solvent Irradiation Exposure on TBP Processing of Spent LMFBR Fuels , HEDL-TME 73-51, 1973 Appendix A. 

The principal long-lived actinide elements that may enter the environment from either U or Pu fuel cycles are Pu, Am, Cm, and Np. Approximately 25% of the alpha activity estimated to be released to the atmosphere from the Liquid Metal Fast Breeder Reactor (LMFBR) fuel cycle will be contributed by 21tlAm, 21 2Cm, and 21fltCm (2)... 

The shorter time allowed for LMFBR fuel to cool is desirable for economic reasons to reduce the amount of plutonium inventory outside of the reactor. The rate at which plutonium is discharged from the LMFBR is eight times as high as from the uranium-fueled LWR (Fig. 3.31) and twice as high as from the LWR with plutonium recycle (Fig. 3.32). 

Extraction Process Having Application to the Reprocessing of LMFBR Fuels, Report ORNL 746, 1972. 

Oak Ridge National Laboratory LMFBR Fuel Cycle Studies Progress Report for July 1971, No. 29, Report ORNL-TM-3534,1971. 

Because some of the sodium coolant used in the LMFBR fuel that may have adhered to the cladding or penetrated leaks in it would react vigorously with water or nitric acid, it is necessary to oxidize all sodium by exposing the fuel to an inert gas containing a controlled amount of water vapor before the dissolution step. LMFBR fuel may not be stored with water cooling till after all sodium has been removed. 

To reduce the specific power somewhat in reprocessing, it is planned to combine irradiated fuel from the LMFBR core with irradiated fuel from the LMFBR blankets in proportion to the rates at which they are discharged from the reactor. Even so, the specific power of LMFBR fuel cooled ISO days is 1.4 times that of LWR fuel cooled the same length of time. 

Tfie concentration of plutonium in combined core and blanket fuel from the LMFBR is more than 10 times that of LWR fuel. This is the most significant difference between the two fuels with respect to reprocessing. Other important differences are the greater amounts of tritium and the 140 percent greater ruthenium activity, and the 60 percent greater overall specific activity of ISO-day cooled LMFBR fuel. 

---