Critical Heat Flux Correlation for Triangular Arrays of Rod Bundles with Tight Lattices, Including the Spiral Spacer Effect-Reference-Cited by-同舟云学术

Critical Heat Flux Correlation for Triangular Arrays of Rod Bundles with Tight Lattices, Including the Spiral Spacer Effect

Published:1985-10 Issue:1 Volume:71 Page:111-124
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Donne Mario Dalle¹,Hame Walter¹

Affiliation:

1. Institut für Neutronenphysik und Reaktortechnik, Kernforschungszentrum Karlsruhe Postfach 3640, D-7500 Karlsruhe, Federal Republic of Germany

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT85-A33713

Reference24 articles.

1. General Features of Advanced Pressurized Water Reactors with Improved Fuel Utilization

2. M. DALLE DONNE and W. HAME, “Parametric Thermohydraulic Study of an Advanced Pressurized Water Reactor with a Tight Fuel Lattice,” KfK-3453, EUR-7059e, Kernforschungszentrum Karlsruhe (1982).

3. M. DALLE DONNE and W. HAME, “A Critical Heat Flux Correlation for Advanced Pressurized Light Water Reactor Application,” KfK-3279, EUR-7057e, Kernforschungszentrum Karlsruhe (1982).

4. “Bettis Atomic Power Laboratory Pressurized Water Reactor Project Technical Progress Report,” WAPD-MRP-92, Westinghouse Electric Corporation (April-June 1961).

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