Optimization of UO2 fueled PWR core design

Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05

Volumn 5, Issue , 2005, Pages 2870-2880

  Greenspan, E ^a   Ganda, F ^a   Olander, D ^a   Shayer, Z ^a   Todreas, N ^b   Malen, J ^b   Shuffler, C ^b   Trant, J ^b   Petrovic, B ^c   Garkisch, H ^c   Romano, A ^d  

^a UNIVERSITY OF CALIFORNIA   (United States)

^b MASSACHUSETTS INSTITUTE OF TECHNOLOGY   (United States)

^c WESTINGHOUSE ELECTRIC COMPANY   (United States)

^d PAUL SCHERRER INSTITUTE   (Switzerland)

Author keywords

[No Author keywords available]

Indexed keywords

DOPPLER COEFFICIENT; URANIUM ENRICHMENT;

COOLANTS; DOPPLER EFFECT; MODERATORS; NUCLEAR FUELS; OPTIMIZATION; PRESSURE DROP; REACTOR CORES;

URANIUM DIOXIDE;

EID: 34249078869     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (15)

1. E. Greenspan, N. Todreas and B. Petrovic, "Use of Solid Hydride for Improved Long-Life LWR Core Designs," NERI Project Number 02-189, 2002.
2. E. Greenspan, H. Garkisch, J. Malen, M. Moalem, D. Olander, B. Petrovic, Z. Shayer and N. Todreas, "Preliminary Assessment of Possibilities for Improving the Performance of LWRs Using Hydride Fuel," American Nuclear Society, 89, 381-382, November 2003.
3. F. Ganda and E. Greenspan, "A Simplified Method for Multi-Batch PWR Core Analysis Based on SAS2H Unit Cell Calculations," Submitted for the Int. Mtg. Mathematics and Computation - MC2005, Avignon, France, September 12-15,2005.
4. O.W. Hermann, C.V. Parks, "SAS2H: A Coupled One-Dimensional Depletion and Shielding Analysis Module, " NUREG-CR-0200, Rev. 6, Vol. 1, Section 2, Oak Ridge National Laboratory, September 1998.
5. "SCALE-5: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation," ORNL RSICC Computer Code Package C00725, June 2004.
6. F. Ganda, D. Barnes and E. Greenspan, "OECD Benchmark A & B of MOX Fueled PWR Unit Cells Using SAS2H," Submitted for the Int. Mtg. Mathematics and Computation - MC2005, Avignon, France, September 12-15, 2005.
7. C Stewart, "VIPRE-01: A Thermal Hydraulic Code for Reactor Cores. Vol 3 Programmer's Manual," July 1985.
8. S. Blair, "Thermal Hydraulic Performance Analysis of a Small Integral PWR Core," Nuclear Engineer's Thesis, MJT, Department of Nuclear Engineering, Sept. 2003.
9. th Int. Conf. on Nuclear Thermal Hydraulics,NUTHOS-6, Nara, Japan, October 4-8, 2004. Paper ID: N6P216.
10. J. A. Malen, N. E. Todreas and A. Romano, "Thermal Hydraulic Design of Hydride Fueled Pressurized Water Reactor Cores", MIT Nuclear Fuel Cycle Technology and Policy Program Report MT-NFC-TR-062, March 2004.
11. G. A. Berna, M. P. Bohn, W. N. Rausch, R. W. Williford and D. D. Lanning, "FRACON-3: A Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods for High Bumup," NUREG/CR-6534, PNNL-11513, Vol. 2, PNL, Richland, Washington, 1997.
12. C. A. Shuffler, "Optimization of Hydride Fueled Pressurized Water Reactor Cores" M.Sc. Dissertation, MIT Department of Nuclear Engineering, August 2004.
13. J. M. Trant, "Transient Analysis of Hydride Fueled Pressurized Water Reactor Cores," M.Sc. Dissertation, MIT Department of Nuclear Engineering, August 2004.
14. J. Saccheri, "A Tight Lattice Epithermal Core Design for the Integral PWR," Ph.D. Dissertation, Department of Nuclear Engineering, MIT, August 2003.
15. NEA/OECD, "The Economics of the Nuclear Fuel Cycle," OECD Publications, Paris, 1994.