Subchannel flow and enthalpy distributions at the exit of a typical nuclear fuel core geometry-Reference-Cited by-同舟云学术

Subchannel flow and enthalpy distributions at the exit of a typical nuclear fuel core geometry

Published:1972-08 Issue:1 Volume:22 Page:19-27
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Castellana Frank S.,Casterline Joseph 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

Reference20 articles.

1. HECTIC-II—An IBM 7090 FORTRAN Computer Program for Heat Transfer Analysis of Gas or Liquid Cooled Reactor Passages;Kattchee;Report No. IDO-28595,1962

2. MANTA—Mixing Analyzed Nodal Thermal-Hydraulic Analyses;Armour;GEAP-4805,1965

3. SASS Code I—Subchannel Analysis for the Steady State;Pierre;AECL-APPE-41,1966

4. HAMBO, A Computer Programme for the Subchannel Analysis of the Hydraulic and Burnout Characteristics of Rod Clusters (Part I) “General Description,”;Bowring;AEEW-R524,1967

5. COBRA-II: A Digital Computer Program For Thermal-Hydraulic Subchannel Analysis of Rod Bundle Nuclear Fuel Elements;Rowe;BNWL-1229,1970

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