HTGR Knowledge Base

Conference Article: Results from integral tests of single reformer tubes under simulated nuclear reactor conditions

Decken, C.B. von der; Fedders, H.; Harth, R.; Hoehlein, B.; Riensche, E. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))

Abstract

The possibility of supplying high temperature heat from a HTGR for process application is being investigated at some places in the world. In all programmes or projects existing with respect to this application, the endothermic steam reforming of methane is one main step in the transmission of heat produced by nuclear fission to different chemical processes. The KFA is involved in the two German projects PNP - Prototypanlage Nukleare Prozesswaerme (Prototype-plant Nuclear Process-heat), and NFE -Nukleare Fernenergie (Long Distance Energy Transport). In a HTGR, helium generally serves as reactor coolant. It transports the heat from the core to the different components which take over this heat for various purposes. In case of arranging a steam reformer in the helium circuit, it is necessary for economic reasons to reach very high temperatures. In the two German projects mentioned above, the helium temperature at HTGR core outlet is determined to 950oC. Thus the main design data for a steam reformer supplied by heat from a HTGR are maximum helium temperature 950oC, helium pressure 40 bar. By an extensive utilization of the available advanced conventional steam reforming technology, the helium heated steam reformer design is using normal steam reforming tubes arranged in compact bundles.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Specialists' meeting on process heat applications technology. Juelich, Germany, F.R. 27 - 29 Nov 1979
International Atomic Energy Agency, Vienna (Austria). International Working Group on High-Temperature Reactors.
IWGHTR--6, pp:134-142