Thermohydraulic Investigations of Decay Heat Removal Systems by Natural Convection for Liquid-Metal Fast Breeder Reactors-Reference-Cited by-同舟云学术

Thermohydraulic Investigations of Decay Heat Removal Systems by Natural Convection for Liquid-Metal Fast Breeder Reactors

Published:1989-12-02 Issue:1 Volume:88 Page:75-86
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Hoffmann Helmut¹,Weinberg Dietrich¹,Ieda Yoshiaki²,Marten Klaus³,Tschöke Herbert³,Frey Hans-Heinz³,Dres Kurt³

Affiliation:

1. Kernforschungszentrum Karlsruhe GmbH Institut fur Reaktorbauelemente, Poslfach 3640 7500 Karlsruhe 1, Federal Republic of Germany

2. Power Reactor and Nuclear Fuel Development Corporation Oarai Engineering Center, Oarai, Japan

3. Kernforschungszentrum Karlsruhe GmbH, Institut fur Reaktorbauelemente Postfach 3640, 7500 Karlsruhe I, 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/NT89-A34338

Reference1 articles.

1. H. M. DOMANUS, R. C. SCHMITT, W. T. SHA, and V. L. SHAH, “COMMIX IB: 3D-Transient Single Phase Computer Program for Thermal Hydraulic Analysis of Single and Multicomponent Systems,” NUREG/CR-4348, ANL-85-42, Vol. I, U.S. Nuclear Regulatory Commission (Sep. 1985).

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