A case study in manual and automated Monte Carlo variance reduction with a deep penetration reactor shielding problem

Nuclear Science and Engineering

Volumn 149, Issue 1, 2005, Pages 23-37

  Smith, Herschel P ^a   Wagner, John C ^b  

^a DUKE ENERGY   (United States)

^b OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; CONVERGENCE OF NUMERICAL METHODS; MATHEMATICAL MODELS; MODERATORS; MONTE CARLO METHODS; PROBLEM SOLVING; TEMPERATURE;

EXCORE DETECTORS; POWER INDICATION; REACTOR TRANSIENTS; SAFETY ANALYSIS;

NUCLEAR REACTORS;

EID: 11444255048     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE05-A2474     Document Type: Conference Paper

References (16)

1. "Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation," U.S. Nuclear Regulatory Commission Information Notice 96-41.
2. "MCNP™ - A General Purpose Monte Carlo N-Particle Transport Code," Version 4C, LA-13709-M, J. F. BRIESMEISTER, Ed. (Dec. 2000).
3. "Validation & Verification of the Dynamic Reactivity Measurement of Rod Worth Technique," North Carolina State University, College of Engineering, Electric Power Research Center Topical Report (2001).
4. J. C. WAGNER, "Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence," MS Thesis, The Pennsylvania State University, The Graduate School College of Engineering (Dec. 1994).
5. "CASMO-4: A Fuel Assembly Burnup Program," STUDSVIK/SOA-95/1.
6. S. P. PEDERSON, R. A. FORSTER, and T. E. BOOTH, "Confidence Interval Procedures for Monte Carlo Transport Simulations," Nucl. Sci. Eng., 127, 54 (1997).
7. J. C. WAGNER, "An Automated Deterministic Variance Reduction Generator for Monte Carlo Shielding Applications," Proc. Radiation Protection & Shielding Division 12th Biennial Topl. Mtg. Radiation Serving Society, April 14-18, 2002, Santa Fe, New Mexico, American Nuclear Society (2002) (CD-ROM).
8. G. I. BELL and S. GLASSTONE, Nuclear Reactor Theory, Van Nostrand and Reinhold, New York (1970).
9. A. HAGHIGHAT and J. C. WAGNER, "Monte Carlo Variance Reduction with Deterministic Importance Functions," Prog. Nucl. Energy, 42, 1, 25 (2003).
10. J. C. WAGNER and A. HAGHIGHAT, "Automated Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinales Adjoint Function," Nucl. Sci. Eng., 128, 186 (1998).
11. C. N. CULBERTSON and J. S. HENDRICKS, "An Assessment of MCNP Weight Windows," LA-13668, Los Alamos National Laboratory (1999).
12. "DOORS 3.2: One, Two- and Three-Dimensional Discrete Ordinales Neutron/Photon Code System," CCC-650, Radiation Safety Information Computational Center, Oak Ridge National Laboratory.
13. "BUGLE-96: Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications," DLC-185, Radiation Safety Information Computational Center, Oak Ridge National Laboratory.
14. 3 Cross Sections for Shipping Cask Analysis," DLC-23, Radiation Safety Information Computational Center, Oak Ridge National Laboratory.
15. J. C. WAGNER, "Acceleration of Monte Carlo Shielding Calculations with an Automated Variance Reduction Technique and Parallel Processing," PhD Thesis, The Pennsylvania State University, The Graduate School College of Engineering (Dec. 1997).
16. H. P. SMITH, "In-Situ Benchmark of MCNP Computer Code Reactor Quarter-Core and Detector Model," Trans. Am. Nucl. Soc., 89, 559 (2003).