نتایج جستجو برای: thermal hydraulics

تعداد نتایج: 218671  

Journal: :Computers & Chemical Engineering 2007
M. Gadalla Laureano Jiménez Z. Olujic P. J. Jansens

This paper presents a new approach to the conceptual design of internally heatintegrated distillation columns (i-HIDiC), based on column temperature profiles analysis. The paper proposes tools to assess the thermal feasibility of i-HIDiC designs and to determine whether the design and operation are feasible from the hydraulics’ point of view.

2007
Richard Procassini Kyle Chand Christopher Clouse Robert Ferencz Jeffrey Grandy William Henshaw Kevin Kramer Dennis Parsons Lawrence Livermore

To meet the simulation needs of the GNEP program, LLNL is leveraging a suite of high-performance codes to be used in the development of a multi-physics tool for modeling nuclear reactor cores. The Osiris code project, which began last summer, is employing modern computational science techniques in the development of the individual physics modules and the coupling framework. Initial development ...

Journal: :Journal of Nuclear Science and Technology 1997

2008
J. Jiménez M. Avramova D. Cuervo K. Ivanov

The aim of the research described in this paper is to perform consistent comparative analyses of two different approaches for coupling of two-scale, two-physics phenomena in reactor core calculations. The physical phenomena of interest are the neutronics and the thermal-hydraulics core behaviors and their interactions, while the spatial scales are the “global” (assembly/channel-wise) and the “l...

2002
M. E. Sawan

A breeding blanket design for the tritium production ICF reactor SIRIUS-T is presented. The blanket consists of alternating layers of beryllium multiplier and lithium breeder/coolant with vanadium alloy structure. A tritium breeding ratio of 1.9 can be achieved for the optimum layered configuration with lithium enriched to 90% 6Li. An optimum coolant routing scheme is utilized to achieve adequa...

2014
Mohammad Pourgol-Mohammad Seyed Mohsen Hoseyni

Results of the codes simulating transients and abnormal conditions in nuclear power plants are inevitably uncertain. In application to thermal-hydraulic calculations by thermal-hydraulics codes, uncertainty importance analysis can be used to quantitatively confirm the results of qualitative phenomena identification and ranking table (PIRT). Several methodologies have been developed to address u...

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