Investigations on Monte Carlo based coupled core calculations

Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"

Volumn 2, Issue , 2008, Pages 797-806

  Tippayakul, C ^a   Avramova, M ^a   Espel, F Puente ^a   Ivanov, K ^a  

^a PENNSYLVANIA STATE UNIVERSITY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; BOUNDARY CONDITIONS; BOUNDARY VALUE PROBLEMS; CHLORINE COMPOUNDS; CODES (STANDARDS); CODES (SYMBOLS); COUPLED CIRCUITS; CRITICALITY (NUCLEAR FISSION); DECISION MAKING; ELECTRIC POWER PLANTS; EXTRACTION; FEEDBACK; FLUID MECHANICS; HYDRAULICS; MANAGEMENT SCIENCE; MATHEMATICAL MODELS; NUCLEAR ENERGY; NUCLEAR ENGINEERING; NUCLEAR INDUSTRY; NUCLEAR POWER PLANTS; NUCLEAR PROPULSION; NUCLEAR REACTORS; PLANNING; POWER PLANTS; REACTOR CORES; RESOURCE ALLOCATION; STATE FEEDBACK; STEAM POWER PLANTS; THREE DIMENSIONAL;

BOILING WATER REACTOR (BWR); CELL BASED; CODE MODIFICATIONS; COMPUTATION PROCESSES; CONTINUOUS ENERGY MONTE CARLO METHOD; CORE CALCULATIONS; CORE DESIGNS; CRITICALITY CALCULATIONS; DIFFUSION MONTE CARLO; FEASIBILITY STUDIES; GEOMETRY COMPLEXITY; HIGH-ACCURACY; INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS; MONTE CARLO; NUCLEAR RENAISSANCE; PENNSYLVANIA STATE UNIVERSITY; RADIAL BOUNDARY CONDITIONS; THERMAL-HYDRAULIC; THREE DIMENSIONAL (3D);

MONTE CARLO METHODS;

EID: 52249123883     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (15)

1. RSIC Computer Code Collection,"'MCNP5 Monte Carlo N-Particle Transport Code System", Oak Ridge National Laboratory, April 2003.
2. MacFarlane, "NJOY 99.81 Code System for Producing Point-wise and Multi-group Neutron and Photon Cross Sections from ENDF/B data", Los Alamos, New Mexico.
3. T. Beam, K. Ivanov, A. Baratta, H. Finnemann, "Nodal Kinetics Model Upgrade in the Penn State Coupled TRAC/NEM Codes", Annals of Nuclear Energy, Vol. 26, pp. 1205-1219 (1999)
4. M. Avramova, D. Cuervo, K. Ivanov, "Improvements and Applications of COBRA-TF for Stand-Alone and Coupled LWR Safety Analyses", Proc. Of PHYSOR-2006 Conference, Vancouver, Canada (2006).
5. S. van der Marek, R. Meulekamp, A.Hogenbirk, "New Temperature Interpolation in MCNP", Proc. of the M&C 2005 Conference, Avignon, France (2005).
6. F. Brown, "On the Use of Shannon Entropy of the Fission Distribution for Assessing Convergence of Monte Carlo Criticality Calculations", Proc. Of PHYSOR-2006 Conference, Vancouver, Canada (2006).
7. C. Tippayakul, "Development of a Practical Fuel Management System for PSBR Based on Advanced Three-Dimensional Monte Carlo Coupled Depletion Methodology", PhD Thesis, The Pennsylvania State University (2006).
8. S. van der Marek, J. Kuijper, J. Oppe, "Homogenized Group Cross-Sections by Monte Carlo", Proc. Of PHYSOR-2006 Conference, Vancouver, Canada (2006).
9. M. Tohjoh, M. Watanabe, A. Yamamoto, "Application of Continuous-Energy Monte Carlo Code as a Cross-Section Generator for BWR Core Calculations", Annals of Nuclear Energy, Vol. 32, pp. 857-875 (2005).
10. C. Waata, T. Schulenberg and X. Cheng, "Coupling of MCNP with a Sub-Channel Code for Analysis of a HPLWR Fuel Assembly," Proc. of the 11' International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Avignon, France (2005).
11. H. J. Shim, B. S. Han, and C. H. Kim, "Numerical Experiment on Variance Biases and Monte Carlo Neutronics Analysis with Thermal Hydraulic Feedback," Proc. of the SNA 2003, Paris, France (2003).
12. V. Sanchez, B. Becker, C. H. M. Broeders, and P. Vinson, "A Procedure for Coupled Neutron Physics / Thermal Hydraulic Calculation of the Pin-wise Power Distribution within a Fuel Assembly," Proc. of the Annual Meeting of Nuclear Technology, Aachen, Germany (2006).
13. N. Kriangchaiporn, "Advanced Fuel Management System (AFMS) for PSBR", M.S. Thesis, The Pennsylvania State University (2001).
14. HELIOS Methods, StudsvikScandpower (2000)
15. V. Xulubana, "Accuracy Evaluation of the Peak Pin Exposure Calculations in Current LWR Core Design Codes", MS Thesis, The Pennsylvania State University (2006).