Berechnung und Analyse eines HTR-Referenzcores im (U, Pu)- und im (U, Th)-Zyklus mit dem neu erstellten modularen Programmsystem DRAKULA-II
Berechnung und Analyse eines HTR-Referenzcores im (U, Pu)- und im (U, Th)-Zyklus mit dem neu erstellten modularen Programmsystem DRAKULA-II
In this report the new modular programme system ORAKULA II (twodimensional diffusion reactor and burn-up programme with ball layout II) is presented. Calculations for the First years of operation of each reference core for the process he g t pebble-bed reactor PR 500 in the low enriched (U, Pu) and...
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Personal Name(s): | Hoffmann, K. (Corresponding author) |
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Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
Imprint: |
Jülich
Kernforschungsanlage Jülich, Verlag
1975
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Physical Description: |
82 p. |
Document Type: |
Report Book |
Research Program: |
Addenda |
Series Title: |
Berichte der Kernforschungsanlage Jülich
1251 |
Link: |
OpenAccess |
Publikationsportal JuSER |
In this report the new modular programme system ORAKULA II (twodimensional diffusion reactor and burn-up programme with ball layout II) is presented. Calculations for the First years of operation of each reference core for the process he g t pebble-bed reactor PR 500 in the low enriched (U, Pu) and for the HHT-1000 MW$_{el}$ in the thorlum cycle (U, Th) are carried out . The essential innovationsof the modular programme system are the Integration of a one-dimensional spectral programme for the comprehension of all heterogeneity effects of the spatial and energetic microstructure of a pebble-bed reactor, the consideration of the thermodynamic feedback on the burn-up behaviour with a modularly integrated temperature programme and the coupling of a very flexible evaluationmodulus for a detailled plotting of all interesting reactor physical parameters. A short description of the programme system is given. Investigations are undertaken on the burn-up and temperature dependence of the resonance adsorption and the flux lowering in a fuel ball as well as the influence of the heterogeneous fuel distribution in a ball-shaped fuel element on the neutron spectrum. The feedback of these effects an the burn-up behaviour is analysed in the subsequent calculations of the above-mentioned reference cores.Beyond this a comparison of the DRAKULA II results with the VSOP calculations for these reference cores is performed and discussed.Especially the new graphical plotting possibility has to be mentioned for the burn-up and load condition of individual fuel element balls during their flow through the core in addition with the netto Balance of the Isotope vector at their removal from the reactor. |