Barnwell Nuclear Fuel Plant

AGNS Staff, Engineering Evaluations of alternativesfor Processing Uranium-Based Fuels, Studies and Research Concerning the Barnwell Nuclear Fuels Plant (BNFP), AGNS-1040-3.1-32, National Technical Information Service (NTlS), Springfield, Va., 1978. 

Name Location Hanford, Wash. Savannah River, S.C. Idaho Chemical Processing Plant Idaho National West Valley, N.Y. Barnwell Nuclear Fuel Plant Barnwell, S.C. 

The Barnwell Nuclear Fuel Plant is the newest U.S. reprocessing plant. In 1979, it was nearly complete, but standing unused because of U.S. government policy unfavorable to reprocessing fuel from power reactors. Its main process features are to be described in Sec. 4.14 as an example of a modem Purex plant. 

The other three reductants are free of this disadvantage, but introduce process complications. Simultaneous cathodic reduction and partitioning has been patented by Allied-General [G13] and is proposed for use in the Barnwell Nuclear Fuel Plant (Sec. 4.14), but it has not yet been used commercially. It requires a novel, electrolytic reduction extraction contactor. 

Fig. 10.11 Process flow diagram for solvent extraction section of Barnwell Nuclear Fuel Plant, x x-x solids -aqueous --organic . vapor.

Use of these Purex equilibrium charts will be illustrated by calculating the number of equilibrium extracting and scrubbing stages needed in the uranium decontamination unit 2D of the Barnwell Nuclear Fuel Plant, data for which were given in Fig. 10.11 and Tables 10.7 and... 

Table 10.10 Adjusted material balance for calculation of number of theoretical stages in uranium decontamination unit 2D of Barnwell Nuclear Fuel Plant"... 

Figure 10.18 Nomenclature for uranium-nithenium-nitric acid separation example, unit 2D of Barnwell Nuclear Fuel Plant.

Allied-General Nuclear Services Barnwell Nuclear Fuel Plant Environmental Statement, Jan. 1974. 

Allied-General Nuclear Services Final Safety Analysis Report, Barnwell Nuclear Fuel Plant Separations Facility, Oct. 1973. 

Show that the concentration proposed for the solution to be fed to the Barnwell Nuclear Fuel Plant, containing 1.21 mol of uranium, 2.9 g of plutonium and 5.6 g of gadolinium per liter, would be subcritical even with fuUy enriched U. 2200 m/s cross sections are accurate enough for this cheek. 

For brevity, the Barnwell Nuclear Fuel Plant is referred in this chapter as the AGNS plant, an abbreviation for the plant owner. Allied General Nuclear Services. 

Preliminary Safety Analysis Rqmrt. Allied-Gulf Nuclear Services, Barnwell Nuclear Fuel Plant, Addendum 7, Plutonium Product Facility, July 1974, Docket No. 50-332. 

This approach has been aiq >lied successfully in the analysis of the Barnwell Nuclear Fuel Plant s Uranium Hexafluoride (UF,) Facility, and should have applicabUity to other facilities. 

This paper describes the plans for the use of gadolinium nitrate for criticality control in the dissolver system at the Barnwell Nuclear Fuel Plant (BNFP). The particular aspects this paper addresses include (a) a description of the poison solution makeup system and its safety-related controls, and (b) a summary of the criticality analysis of the dissolver unit. 

G. A. TOWNES, M. L. ROGELL, and R. T. ANDERSON, Spent Fuel Disassembly and Canning Programs at the Barnwell Nuclear Fuel Plant, AGNS-3S900-1.2<45, Allied-General Nuclear Services (1979). 

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