Thermal and hydraulic design

Information shall be provided to prove that, during operational states, adequate core cooling capacity will be available to keep the reactor fuel in a thermally safe condition and that an adequate thermal safety margin will be available to prevent or minimize fuel damage in accident conditions. 

Basic information on thermal and hydraulic core design shall include  

All safety related hydraulic characteristics of individual core components and of the core as a whole (such as average and local coolant velocities, and coolant pressures, as appropriate) for operational states during forced and natural convection cooling. 

The power distribution in all core components which may contain fissile materials, as derived from the nuclear design characteristics provided in para. A.514(b). 

The information shall be qualified by reference to analyses, experimental measurements, fabrication specifications, etc, from which it is derived, thus providing a quantitative assessment of the uncertainties in each of the safety relevant parameters that have been quantified. 

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Thermal and Hydraulic Design Parameters APIOOO AP600 Typical XL Plant... 

Hewitt, G. E, ed. 2008. HEDH Heat Exchanger Design Handbook, rev. ed. New York Begell House. This five-volume set is divided into broad topical areas theory, fluid mechanics, and heat transfer, thermal and hydraulic design of heat exchangers, mechanical design of heat exchangers, and physical properties. This last section is particularly data-focused. 

J.A.G., OBERTELLI J.D. and Thermal and hydraulic design Paper 5, BNES Conference,... 

Nakata, T., Katanishi, S., Takada, S., Yan, X., Kunitomi, K., 2003. Nuclear, thermal and hydraulic design for gas turbine high temperature reactor (GTHTR300). AESJ Transaction 2 (4), 478-489. 

G. P. Purohit, Thermal and hydraulic design of hairpin and finned-bundle exchangers, Chemical Engineering, May 16,1983, pp. 62-70. 

Modification of some design parameters, Figure 8.13(c), then rerating the design to meet thermal and hydraulic specifications and economic requirements. 

The main objective of this chapter is to survey some of the important literature pertinent to each enhancement technique, thus providing guidance for potential users. With the large amount of literature in the field, it is clearly impossible to cite more than representative studies. Wherever possible, correlations for thermal and hydraulic performance will be presented, or key sources of design data will be suggested. 

Later in the project after the main parameters had been fixed it was necessary to build up a detailed picture of the expected performance tracing the interactions between the nuclear and thermal hydraulic aspects. This led to the development of the PATRIARCH scheme (see Pig. 1) of computer codes which forms a set of modular compatible programmes designed to cover all performance aspects. It was of course necessary to relate the development of PATRIARCH very closely to the flow of data arising from the experimental reactor physics programme and from the thermal and hydraulic rigs (ref. 4). 

The choice of cladding requires consideration of thermal and hydraulic requirements, material compatibility, and fission gas buildup. Aluminum, stainless steel, zircaloy, and molybdenum are possible candidates. The stainless steel and molybdenum alloys are acceptable based on their material strength and ability to withstand longterm irradiation as compared to the traditional zir-caloys. For optimal heat removal, the design should minimize fuel-to-clad gaps at normal operating conditions. This can be achieved by... 

The complete design of an IHX must consider thermal and hydraulic performance, accommodations for differential thermal expansion, provision for maintenance, and fabrication. As such, the physical configuration of the unit plays a significant role in the performance, reliability, maintainability, and economics of a heat exchanger. 

N. E. Todreas and M. S. Ka2imi, Nuclear Systems I Thermal Hydraulic Fundamentals, 1989, II Elements of Thermal Hydraulic Design, 1990, Hemisphere Publishing Corp., New York. 

Enhancement of CHF subcooled water flow boiling was sought to improve the thermal hydraulic design of thermonuclear fusion reactor components. Experimental study was carried out by Celata et al. (1994b), who used two SS-304 test sections of inside diameters 0.6 and 0.8 cm (0.24 and 0.31 in.). Compared with smooth channels, an increase of the CHF up to 50% was reported. Weisman et al. (1994) suggested a phenomenological model for CHF in tubes containing twisted tapes. 

Akoski, J., R. D. Watson, P. L. Goranson, A. Hassanian, and J. Salmanson, 1991, Thermal Hydraulic Design Issues and Analysis for ITER Diverters, Fusion Technol. 79.-1729—1735. (4)... 

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