HEAT PIPE HEAT EXCHANGER FOR HIGH TEMPERATURE NUCLEAR REACTOR TECHNOLOGY

摘要：

　　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 superheatedRankine 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.

关键词： Heat pipe heat exchanger sodium working fluid,tritium,nuclear reactor

作者: R.T.Dobson R Laubscher

作者单位: Department of Mechanical Engineering, University of Stellenbosch Private Bag X1, Stellenbosch 7602, South Africa

会议类型: 国际会议

会议名称: The 11th International Heat Pipe Symposium(第十一届国际热管研讨会)

会议地点: 北京

会议语种:英文

页码: 218-226

在线出版日期: 2013-06-09（万方平台首次上网日期，不代表论文的发表时间）