SHOVAV JÜL : ein eindimensionales Neutronenkinetikprogramm für Kugelhaufen Hochtemperaturreaktoren mit Temperatur- und Xenon- Rückkopplung
SHOVAV JÜL : ein eindimensionales Neutronenkinetikprogramm für Kugelhaufen Hochtemperaturreaktoren mit Temperatur- und Xenon- Rückkopplung
The present report describes the modelling basis and the structure of the neutron kinetics-code SHOVAV-Jlil. Information for users is given regarding the application of the code and the generation of the input data. SHOVAV-Jül is a one-dimensional space-time-code based on a multigroup diffusion appr...
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Personal Name(s): | Nabbi, Rahim |
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Meister, G. / Finken, R. / Haben, M. | |
Contributing Institute: |
Publikationen vor 2000; PRE-2000; Retrocat |
Imprint: |
Jülich
Kernforschungsanlage Jülich GmbH Zentralbibliothek, Verlag
1982
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Physical Description: |
77, A30, B39 p. |
Document Type: |
Report Book |
Research Program: |
ohne Topic |
Series Title: |
Spezielle Berichte der Kernforschungsanlage Jülich
171 |
Link: |
OpenAccess |
Publikationsportal JuSER |
The present report describes the modelling basis and the structure of the neutron kinetics-code SHOVAV-Jlil. Information for users is given regarding the application of the code and the generation of the input data. SHOVAV-Jül is a one-dimensional space-time-code based on a multigroup diffusion approach for four energy groups and six groups of delayed neutrons It.has been developed for the analysis of the transient behaviour of high temperature reactors with pebble-bed core. The reactor core is modelled by horizontal segments to which different materials compositions can be assigned. The temperature dependence of the reactivity is taken into account by using temperature dependent neutron cross sections. For the simulation of transients in an extended time range the time dependence of the reactivity absorption by Xenon-135 is taken into account. The code starts always from a steady state as an initial condition for transient calculations. The steady state can be achieved by iterative adaptation of selected core parameters. Perturbations of the neutron balance can be inpressed by time dependent variation of the reactivity,the core composition and the control rod position or by time dependent boundary conditions such as coolant mass flow, coolant inlet temperature and steam content in the core. The code contains a one-dimensional thermohydraulic model for the core which calculates steady state and transient temperature distributions of the fuel, the moderator and the coolant. For the analysis of steam ingress accidents the coolant may be treated as a mixture of helium and water steam. |