Published October 1980 | Version v1
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Results from integral tests of single reformer tubes under simulated nuclear reactor conditions

  • 1. Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)

Description

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 9500C. Thus the main design data for a steam reformer supplied by heat from a HTGR are maximum helium temperature 9500C, 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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Additional details

Publishing Information

Imprint Title
Specialists' meeting on process heat applications technology, Kernforschungsanlage Juelich GmbH., Federal Republic of Germany, 27-29 November 1979
Imprint Pagination
170 p.
Journal Page Range
p. 134-142.
Report number
IWGHTR--6

Conference

Title
Specialists' meeting on process heat applications technology.
Dates
27 - 29 Nov 1979.
Place
Juelich, Germany, F.R.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
13696654
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DIAGRAMS; HEAT EXCHANGERS; HTGR TYPE REACTORS; HYDROGEN; PERFORMANCE TESTING; PILOT PLANTS; PROCESS HEAT REACTORS; TUBES
Descriptors DEC
ELEMENTS; FUNCTIONAL MODELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; INFORMATION; NONMETALS; POWER REACTORS; REACTORS; TESTING