Beitrag zum Vergleich von stab- und kugelförmigen Brennelementen für Hochtemperaturreaktoren
Beitrag zum Vergleich von stab- und kugelförmigen Brennelementen für Hochtemperaturreaktoren
Fuel rods and fuel balls for high-temperature reactors are calculated and compared with each other an the basis of a 600 MWe power plant with regard to temperature distributions and thermodynamic sizes in wide-range parameter fields. The different fuelrods are reduced to simple models with reference...
Saved in:
Personal Name(s): | Heil, J. (Corresponding author) |
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Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
Imprint: |
Jülich
Kernforschungsanlage Jülich, Verlag
1972
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Physical Description: |
116 p. |
Document Type: |
Report Book |
Research Program: |
Addenda |
Series Title: |
Berichte der Kernforschungsanlage Jülich
894 |
Link: |
OpenAccess |
Publikationsportal JuSER |
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245 | |a Beitrag zum Vergleich von stab- und kugelförmigen Brennelementen für Hochtemperaturreaktoren | ||
260 | |a Jülich |c 1972 |b Kernforschungsanlage Jülich, Verlag | ||
300 | |a 116 p. | ||
490 | 0 | |a Berichte der Kernforschungsanlage Jülich |v 894 | |
520 | |a Fuel rods and fuel balls for high-temperature reactors are calculated and compared with each other an the basis of a 600 MWe power plant with regard to temperature distributions and thermodynamic sizes in wide-range parameter fields. The different fuelrods are reduced to simple models with reference to the DRAGON types. The average outlet-temperature of cooling gas is constantly kept at 850 °C, the radial power distribution is varied independently and uniformly to permit a comparison for all cores.Therefrom it was shown in the region of power densities, which are of interest from the nuclear-physical view-point, that fuel rods according to their dimensions can haue lower temperatures than fuel balls . Fuel rods of the pressed model show the lowest fuel temperatures; the surface temperatures, however, do not vary significantly. Fuel and surface temperatures of a pebble-bed core according to the OTTO (Once Through Then Out) loading scheme are incorporated into the comparison, too, and show a decrease particularly of the fuel temperature in comparison to a core of the conventional power distributions. The pressure loss of a core with fuel rods can be kept lower than that of a corresponding pebble-bed . The maximum temperature gradients of fuel balls arising in stationary operation are sometimes much below the values of fuel rods. | ||
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