Channel deformation analysis for fast reactor fuel assemblies undergoing swelling and thermal bowing-Reference-Cited by-同舟云学术

Channel deformation analysis for fast reactor fuel assemblies undergoing swelling and thermal bowing

Published:1972-12 Issue:3 Volume:23 Page:309-320
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ohmae Kenichi,Morino Akikazu,Nakao Noboru,Hirao Seizo

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

Reference7 articles.

1. Nuclear Reactor Core Analysis Code: CITATION;Fowler;ORNL-TM-2496, Rev. I,1970

2. COBRA-HA. A Program for Thermal-Hydraulic Analysis in Very Large Bundles of Fule Pins;Wheeler;BNWL-1422, UC-32,1970

3. Plutonium Fuels for LMFBR-an Extrapolation;Leggett;WHAN-SA-51,1970

4. BOW-V: A CDC-3600 Program to calculate the Equilibrium Configurations of a Thermally Bowed Reactor Core;Kucera;ANL/EBR-014,1970

5. Hydraulic Performance in Rod Bundles of Fast Reactor Fuels-Pressure Drop, Vibration and Mixing Coefficient;Okamoto,1970

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