Statistical Analysis of Reactor Pressure Vessel Fluence Calculation Benchmark Data Using Multiple Regression Techniques-Reference-Cited by-同舟云学术

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Statistical Analysis of Reactor Pressure Vessel Fluence Calculation Benchmark Data Using Multiple Regression Techniques

Published:2003-02 Issue:2 Volume:143 Page:158-163
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Carew John F.¹,Finch Stephen J.²,Lois Lambros³

Affiliation:

1. Brookhaven National Laboratory, Energy Science and Technology Department P.O. Box 5000, Upton, New York 11973-5000

2. State University at Stony Brook, Department of Applied Mathematics and Statistics Stony Brook, New York 11794

3. U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation 11555 Rockville Pike, Rockville, Maryland 20852

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE03-A2326

Reference13 articles.

1. OFFICE OF NUCLEAR REGULATORY RESEARCH, “Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence,” Regulatory Guide 1.190, U.S. Nuclear Regulatory Commission (Mar. 2001).

2. Application of the LEPRICON Unfolding Procedure to the Arkansas Nuclear One-Unit 1 Reactor

3. Theory of a New Unfolding Procedure in Pressurized Water Reactor Pressure Vessel Dosimetry and Development of an Associated Benchmark Data Base

4. see also ORNL/TM-9933, Oak Ridge National Laboratory (Mar. 1986).

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