Effect of power variations across a fuel bundle and within a fuel element on fuel centerline temperature in PHWR bundles in uncrept and crept pressure tubes-Reference-Cited by-同舟云学术

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Effect of power variations across a fuel bundle and within a fuel element on fuel centerline temperature in PHWR bundles in uncrept and crept pressure tubes

Published:2017-04 Issue: Volume:102 Page:245-254
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Onder E.N.,Roubtsov D.,Rao Y.F.,Wilhelm B.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference15 articles.

1. Altiparmakov, D., New capabilities of the lattice code WIMS-AECL. In: Proceedings of PHYSOR 2008. Interlaken, Switzerland, 2008 September 14–19.

2. Altiparmakov, D., Shen, W., Marleau, G., Rouben, B., Evolution of computer codes for CANDU analysis. In: Proceedings of PHYSOR 2010. Pittsburgh, Pennsylvania, USA, 2010 May 914.

3. Thermalhydraulic characteristics for CANFLEX fuel channel using burnable poison in CANDU reactor;Bae;Nucl. Eng. Technol.,2015

4. The effect of a CANDU fuel bundle geometry variation on thermalhydraulic performance;Bae;Ann. Nucl. Energy,2011

5. Twophase turbulent mixing and buoyancy drift in rod bundles;Carlucci;Nucl. Eng. Des.,2004

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