Physics and safety studies of low conversion ratio sodium cooled fast reactors

Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy

Volumn , Issue , 2003, Pages 423-433

  Smith, M A ^a   Morris, E E ^a   Hill, R N ^a  

^a ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

FISSILE BREEDING; FUEL ENRICHMENT; LOW CONVERSION RATIOS; REACTIVITY COEFFICIENTS;

ACCIDENT PREVENTION; COOLANTS; DATA REDUCTION; FISSION PRODUCTS; HEAT TRANSFER; PLUTONIUM; SODIUM; VOLUME FRACTION;

FAST REACTORS;

EID: 2642548275     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (9)

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2. R. N. Hill, D. C. Wade, J. R. Liaw, and E. K. Fujita, "Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle," Nuclear Science and Engineering, 121, 17 (1995).
3. E. E. Morris, M. A. Smith, "Development of Low Conversion Ratio Fast Reactors for Transmutation," ANL-AAA-057, October 2002.
4. H. Henryson II, B. J. Toppel, and C. G. Stenberg, "MC2-2: A Code to Calculated Fast Neutron Spectra and Multigroup Cross Sections," ANL-8144, Argonne National Laboratory (1976).
5. B. J. Toppel, "A User's Guide to the REBUS-3 Fuel Cycle Analysis Capability," ANL-83-2, Argonne National Laboratory (1983).
6. R. D. Lawrence, "The DIF3D Nodal Neutronics Option for Two- and Three-Dimensional Diffusion Theory Calculations in Hexagonal Geometry," ANL-83-1, Argonne National Laboratory (1983).
7. C. H. Adams, "Specifications for VARI3D - A Multidimensional Reactor Design Sensitivity Code," FRA-TM-74, Argonne National Laboratory (1975).
8. J. E. Cahalan, Personal Communication (June 2002).
9. J. E. Cahalan, A. M. Tentner, and E. E. Morris, "Advanced LMR Safety Analysis Capabilities in the SASSYS-1 and SAS4A Computer Codes," Proceedings of ANS 1994 International Topical Meeting on Advanced Reactors Safety, Pittsburg, PA, Vol. 2, pp. 1038-1045, April 17-21, 1994.