Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques-Reference-Cited by-同舟云学术

Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques

Published:2004-03 Issue:3 Volume:146 Page:340-366
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Broadhead B. L.¹,Rearden B. T.¹,Hopper C. M.¹,Wagschal J. J.²,Parks C. V.¹

Affiliation:

1. Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, Tennessee 37831-6370

2. The Hebrew University of Jerusalem Racah Institute of Physics, 91904, Jerusalem, Israel

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE03-2

Reference23 articles.

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2. J. J. LICHTENWALTER, S. M. BOWMAN, M. D. DEHART, and C. M. HOPPER, “Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages,” NUREG/CR-6361 (ORNL/TM-13211), U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory (1997).

3. R. K. DISNEY, “A Review of the Current State-of-the-Art Methodology for Handling Bias and Uncertainty in Performing Criticality Safety Evaluations,” INEL-94/0251, UC-501, Idaho National Engineering Laboratory (1994).

4. “SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing and Evaluations,” NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), Vols. I, II, and III, CCC-545, Radiation Safety Information Computational Center (May 2000).

5. R. L. CHILDS, “SEN1: A One-Dimensional Cross-Section Sensitivity and Uncertainty Module for Criticality Safety Analysis,” NUREG/CR-5719 (ORNL/TM-13738), U.S. Nuclear Regulatory Commission/Oak Ridge National Laboratory (1999).

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