Coupled reactor kinetics and heat transfer model for heat pipe cooled reactors

Details Coupled reactor kinetics and heat transfer model for heat pipe cooled reactors Coupled reactor kinetics and heat transfer model for heat pipe cooled reactors

Feb 2001

adsabs.harvard.edu/cgi-bin/nph-data_query?bibcode=2001aipc..552..815w&link_type=abstract

Space Technology and Applications International Forum - 2001. AIP Conference Proceedings, Volume 552, pp. 815-821 (2001).

Astronomy and Astrophysics

Astronomy

Spaceborne And Space Research Instruments, Apparatus, And Components, Other Topics In Instruments, Apparatus, And Components Common To Several Branches Of Physics And Astronomy

Scientific paper

Heat pipes are often proposed as cooling system components for small fission reactors. SAFE-300 and STAR-C are two reactor concepts that use heat pipes as an integral part of the cooling system. Heat pipes have been used in reactors to cool components within radiation tests (Deverall, 1973); however, no reactor has been built or tested that uses heat pipes solely as the primary cooling system. Heat pipe cooled reactors will likely require the development of a test reactor to determine the main differences in operational behavior from forced cooled reactors. The purpose of this paper is to describe the results of a systems code capable of modeling the coupling between the reactor kinetics and heat pipe controlled heat transport. Heat transport in heat pipe reactors is complex and highly system dependent. Nevertheless, in general terms it relies on heat flowing from the fuel pins through the heat pipe, to the heat exchanger, and then ultimately into the power conversion system and heat sink. A system model is described that is capable of modeling coupled reactor kinetics phenomena, heat transfer dynamics within the fuel pins, and the transient behavior of heat pipes (including the melting of the working fluid). This paper focuses primarily on the coupling effects caused by reactor feedback and compares the observations with forced cooled reactors. A number of reactor startup transients have been modeled, and issues such as power peaking, and power-to-flow mismatches, and loading transients were examined, including the possibility of heat flow from the heat exchanger back into the reactor. This system model is envisioned as a tool to be used for screening various heat pipe cooled reactor concepts, for designing and developing test facility requirements, for use in safety evaluations, and for developing test criteria for in-pile and out-of-pile test facilities. .

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