Designing a new fuel for HFIR - performance parameters for LEU core configurations

American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV

Volumn 2, Issue , 2009, Pages 1101-1112

  Ilas, Germina ^a   Primm III, R T ^a   Gehin, Jess C ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

HFIR; Low enriched fuel; Research reactor

Indexed keywords

COMPUTATIONAL MODEL; CORE CONFIGURATION; CORE DESIGN; CORE PERFORMANCE; ENGINEERING DESIGN; ENRICHED FUELS; FUEL DESIGN; GLOBAL THREAT REDUCTION INITIATIVES; HIGH FLUX ISOTOPE REACTORS; HIGH POWER DENSITY; HIGHLY ENRICHED URANIUM; HIGHLY ENRICHED URANIUM FUELS; LOW-ENRICHED URANIUM FUEL; NATIONAL NUCLEAR SECURITY ADMINISTRATION; NEW MODEL; PERFORMANCE PARAMETERS; REACTOR PERFORMANCE; SIMULATION METHODS; U.S. DEPARTMENT OF ENERGY;

ISOTOPES; NUCLEAR ENERGY; RESEARCH REACTORS; STRUCTURAL DESIGN; TRANSURANIUM ELEMENTS; URANIUM; URANIUM POWDER METALLURGY;

FUELS;

EID: 74549137456     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (13)

1. R. D. CHEVERTON and T. M. SIMS, "HFIR Core Nuclear Design", ORNL-4621, Oak Ridge National Laboratory (1971).
2. R. T. PRIMM III, R. J ELLIS, J. C. GEHIN, D. L. MOSES, J. L. BINDER, and N. XOUBI, "Assumptions and criteria for performing a feasibility study of the conversion of the High Flux Isotope Reactor core to use low-enriched uranium fuel," CD Proceedings, PHYSOR 2006, Vancouver, Canada (2006).
3. R. J. ELLIS, J. C. GEHIN, and R. T. PRIMM III, "Cross section generation and physics modelling in a feasibility study of the conversion of the High Flux Isotope Reactor core to use low-enriched uranium fuel," CD Proceedings, PHYSOR 2006, Vancouver, Canada (2006).
4. "MCNP - A general Monte Carlo n-particle transport code," Version 5, LA-CP-03-0245, Los Alamos National Laboratory (2003).
5. "SCALE: A modular code system for performing standardized computer analyses for licensing evaluations," Version 5.1, Vols. I-III, ORNL/TM-2005/39. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732 (2006).
6. D. R. VONDY, T. B. FOWLER, and G. W. CUNNINGHAM III, "The BOLD VENTURE computation system for nuclear reactor core analysis," Version III, ORNL-5711, Oak Ridge National Laboratory (1981).
7. G. ILAS, J. C. GEHIN, and R. T. PRIMM III, "New cross section processing methodology for HFIR core analysis," CD Proceedings, PHYSOR 2008, Interlaken, Switzerland (2008).
8. M. D. DEHART, "NEWT: A New Transport Algorithm for Two-Dimensional Discrete Ordinates Analysis in Non-Orthogonal Geometries", NUREG/CR-0200, Rev. 7, Vol. 2, Sec. F21 of reference 5, U.S. Nuclear Regulatory Commission (November 2006).
9. W. HAECK and B. VERBOOMEN, "An optimum approach to Monte Carlo burnup," Nuclear Science and Engineering, 156, 180 (2007).
10. RSICC Computer Code Collection CCC-371, ORIGEN 2.2. Available from RSICC, Oak Ridge National Laboratory (2002).
11. N. XOUBI and R. T. PRIMM III, "Investigation of beryllium internal reflector installation on the fuel cycle length of the High Flux Isotope Reactor," ORNL/TM-2004/252, Oak Ridge National Laboratory (2005).
12. H. A. MCLAIN, "HFIR Fuel Element Steady State Heat Transfer Analysis," Revised Version, ORNL/TM-1904, Oak Ridge National Laboratory, 1967, as appended by T. E. Cole, L. F. Parsly, and W. E. Thomas, "Revisions to the HFIR Steady State Heat Transfer Analysis Code," ORNL/CF-85/68 (1986).
13. R. T. PRIMM III, G. ILAS, and C. GALVEZ VELIT, "Status of design effort for LEU fuel for the High Flux Isotope Reactor," RERTR-2008 International Meeting on Reduced Enrichment for Research and Test Reactors, Washington, D.C. (2008).