Coolant mixing in a fuel pin assembly utilizing helical wire wrap spacers-Reference-Cited by-同舟云学术

Coolant mixing in a fuel pin assembly utilizing helical wire wrap spacers

Published:1973-03 Issue:3 Volume:24 Page:393-409
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Collingham R.E.,Thorne W.L.,McCormack J.D.

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

Reference10 articles.

1. A Thermal-Hydraulic Subchannel Analysis for Rod Bundle Nuclear Fuel Elements;Rowe,1970

2. Turbulent Flow Thermal-Hydraulic Characteristics of Hexagonal Pitch Fuel Assemblies;Oberjohn,1970

3. Experimental Study of Coolant Cross-Mixing in Multirod Bundles, Consisting of Unifinned, One-, Three-, and Six-Fin Fuel Rods;Baumann;Atomkernenergie (ATKE) 14–56,1969

4. Transfer of Coolant Between Adjacent Subchannels in Wire Wrap and Grip Spacer Rod Bundles;Marian;ANS Trans. Winter,1970

5. Edge-Channel Flow in a 19-rod-LMFBR Fuel Assembly;Fontana;Trans. Am. Nucl. Soc.,1972

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