A Case Study in Manual and Automated Monte Carlo Variance Reduction with a Deep Penetration Reactor Shielding Problem

Author:

Smith Herschel P.1,Wagner John C.2

Affiliation:

1. Duke Energy Corporation, 422 South Church Street, P.O. Box 1006, Charlotte, North Carolina 28242

2. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, Tennessee 37831-6170

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference14 articles.

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. Confidence Interval Procedures for Monte Carlo Transport Simulations

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