Heat pipe heat exchanger for high temperature nuclear reactor technology

Dobson, Robert T. ; Laubscher, Ryno (2013)

CITATION: Dobson, R. T. & Laubscher, R. 2013. Heat pipe heat exchanger for high temperature nuclear reactor technology, Frontiers in Heat Pipes, 4, 023002, doi:10.5098/fhp.v4.2.3002.

The original publication is available at http://www.thermalfluidscentral.org


ENGLISH ABSTRACT: When a high temperature nuclear reactor is used to supply process heat, nuclear regulators require an intermediate heat transfer loop between the primary reactor coolant stream and the secondary process heat stream. A sodium-charged heat pipe heat exchanger design is presented that circumvents the need for an intermediate coolant loop. This is done by physically separating the reactor coolant and secondary coolant by two pipe walls, and a vapour section and a liquid section. This tritium diffusion resistant design for the re-heater, preheater, steam generator and super-heater heat supply system of a 232 MW-electrical pebble bed modular reactor heat source for a superheated Rankine power cycle is presented. A theoretical model was then used to produce preliminary design sizes (tube sizes, tube lengths, working fluid, etc.) for a sodium-charged heat exchanger to be used with a high temperature gas-cooled reactor.

AFRIKAANSE OPSOMMING: Geen opsomming beskikbaar

Please refer to this item in SUNScholar by using the following persistent URL: http://hdl.handle.net/10019.1/89325
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