Author: Frederick G. Hammitt
Publisher:
ISBN:
Category :
Languages : en
Pages : 34

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Author: Henri Fenech
Publisher: Elsevier
ISBN: 148315078X
Category : Science
Languages : en
Pages : 591

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Book Description
Heat Transfer and Fluid in Flow Nuclear Systems discusses topics that bridge the gap between the fundamental principles and the designed practices. The book is comprised of six chapters that cover analysis of the predicting thermal-hydraulics performance of large nuclear reactors and associated heat-exchangers or steam generators of various nuclear systems. Chapter 1 tackles the general considerations on thermal design and performance requirements of nuclear reactor cores. The second chapter deals with pressurized subcooled light water systems, and the third chapter covers boiling water reactor systems. Chapter 4 tackles liquid metal cooled systems, while Chapter 5 discusses helium cooled systems. The last chapter deals with heat-exchangers and steam generators. The book will be of great help to engineers, scientists, and graduate students concerned with thermal and hydraulic problems.

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 4

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The Thermal-Hydraulic Out of Reactor Safety (THORS) Program at Oak Ridge National Laboratory (ORNL) had as its objective the testing of simulated, electrically heated liquid metal reactor (LMR) fuel assemblies in an engineering-scale, sodium loop. Between 1971 and 1985, the THORS Program operated 11 simulated fuel bundles in conditions covering a wide range of normal and off-normal conditions. The last test series in the Program, THORS-SHRS Assembly 1, employed two parallel, 19-pin, full-length, simulated fuel assemblies of a design consistent with the large LMR (Large Scale Prototype Breeder -- LSPB) under development at that time. These bundles were installed in the THORS Facility, allowing single- and parallel-bundle testing in thermal-hydraulic conditions up to and including sodium boiling and dryout. As the name SHRS (Shutdown Heat Removal System) implies, a major objective of the program was testing under conditions expected during low-power reactor operation, including low-flow forced convection, natural convection, and forced-to-natural convection transition at various powers. The THORS-SHRS Assembly 1 experimental program was divided up into four phases. Phase 1 included preliminary and shakedown tests, including the collection of baseline steady-state thermal-hydraulic data. Phase 2 comprised natural convection testing. Forced convection testing was conducted in Phase 3. The final phase of testing included forced-to-natural convection transition tests. Phases 1, 2, and 3 have been discussed in previous papers. The fourth phase is described in this paper. 3 refs., 2 figs.

Author: James M. Jacobs
Publisher:
ISBN:
Category : Liquid metals
Languages : en
Pages : 148

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Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 640

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Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 150

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Author:
Publisher:
ISBN:
Category : Bismuth
Languages : en
Pages : 148

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Author: Yu S. Tang
Publisher: American Nuclear Society
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 432

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Book Description
This monograph is written as a treatise on the state-of-the-art of liquid-metal fast breeder reactor thermal and hydraulic design and analysis.

Author: Frederick G. Hammitt
Publisher:
ISBN:
Category :
Languages : en
Pages : 42

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Author: Boro Malinovic
Publisher:
ISBN:
Category :
Languages : en
Pages : 198

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