Fast neutron fluence calculations as support for a BWR pressure vessel and internals surveillance program-Reference-Cited by-同舟云学术

Fast neutron fluence calculations as support for a BWR pressure vessel and internals surveillance program

Published:2010-06 Issue:6 Volume:240 Page:1271-1280
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lucatero Marco A.,Palacios-Hernández Javier C.,Ortiz-Villafuerte Javier,Xolocostli-Munguía J. Vicente,Gómez-Torres Armando M.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference22 articles.

1. American Society for Testing and Materials (ASTM), 2001. Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance E706 (IID). ASTM E 482 – 01.

2. Westinghouse AP1000 internals heating rate distribution calculation using a 3D deterministic transport method;Botta;Nuclear Engineering and Design,2006

3. Brookhaven National Laboratory (BNL), 1997. PWR and BWR pressure vessel fluence calculation benchmark problems and solutions. U.S. Nuclear Regulatory Commission, NUREG/CR-6115, BNL-NUREG-52395.

4. Chowdhury, P., Williams, M.L., Kam, F.B.K., 1988. Development of a three-dimensional flux synthesis program and comparison with 3D transport theory results. NUREG/CR-4984, ORNL/TM-10503.

5. Comisión Federal de Electricidad (CFE), 1979 (and amendments). Laguna Verde Nuclear Power Station Units 1 & 2 Final Safety Analysis Report.

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