Published January 1976
| Version v1
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Formulae for thermal feedback of group constants in digital reactor simulation
Description
The problem, how the feedback of the thermohydraulic field to the neutron density in a reactor can be calculated is analysed. After a brief survey of the digital models in reactor simulation the applied model based on the time-dependent two-group diffusion equations is described. Using the reactor physical code system THERESA numerical results for the VVER-440 reactor are presented. (Sz.Z.)
Availability note (English)
MF available from INIS under the Report Number.Files
7271430.pdf
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Additional details
Publishing Information
- ISBN
- 9633710995
- Imprint Pagination
- 46 p.
- Report number
- KFKI--76-3
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Hungary
- INIS RN
- 7271430
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- DIFFUSION; FEEDBACK; FUNCTIONAL MODELS; NEUTRON DENSITY; REACTOR KINETICS; REACTOR SIMULATORS; SIMULATION; T CODES
- Descriptors DEC
- ANALOG SYSTEMS; COMPUTER CODES; KINETICS; SIMULATORS
Optional Information
- Notes
- 16 refs.; 14 tabs.