Distributed resistance modeling of wire-wrapped rod bundles-Reference-Cited by-同舟云学术

Distributed resistance modeling of wire-wrapped rod bundles

Published:1987-10 Issue:1 Volume:104 Page:93-102
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ninokata Hisashi,Efthimiadis Apostolos,Todreas Neil E.

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

Reference17 articles.

1. COBRA-IIIC: A digital computer program for steady-state and transient thermal-hydraulic analysis of nuclear fuel elements;Rowe;Battelle Pacific Northwest Laboratories, BNWL-1695,1973

2. ASFRE-III: A computer program for triangular rod array thermohydraulic analysis of fast breeder reactors;Ninokata;PNC Report, PNC N941 85–106,1985

3. The SABRE code for fuel rod cluster thermohydraulics;Macdougall;Nucl. Eng. Des.,1984

4. Development work on SABRE code;LeGuez,1982

5. Thermal-hydraulic evaluation of advanced wirewrap assemblies;Wei,1977

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