Influence of power density and burn-up distributions on temperature fields of pebble-bed cores (in German)
Conference
·
· Atomkernenergie, v. 25, no. 2, pp. 125-128
OSTI ID:4130618
The calculation of coolant gas flow and heat transfer in cores of pebble- bed reactors requires special treatment of the fluid dynamics equations. Errors of the approximations and influence of errors of the input data of the calculation are estimated. It can be seen, that power density distribution has to be calculated better than 5% in order to get reasonable results from the calculations. Using for example certain parts of AVR reactor lifetime, the feasibility of influencing the temperature distribution of a pebble-bed reactor by fuel management is demonstrated. By choice of suitable measures, great effects can be obtained. (orig.)
- Research Organization:
- Arbeitsgemeinschaft Versuchs-Reaktor G.m.b.H., Juelich (F.R. Germany)
- NSA Number:
- NSA-33-011240
- OSTI ID:
- 4130618
- Conference Information:
- Journal Name: Atomkernenergie, v. 25, no. 2, pp. 125-128
- Country of Publication:
- Germany
- Language:
- German
Similar Records
Survey of Dust Production in Pebble Bed Reactors Cores
The importance of the AVR pebble-bed reactor for the future of nuclear power
Long-term behavior of the AVR-core
Journal Article
·
Wed Jun 01 00:00:00 EDT 2011
· Nuclear Engineering and Design
·
OSTI ID:1015830
The importance of the AVR pebble-bed reactor for the future of nuclear power
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:22039673
Long-term behavior of the AVR-core
Conference
·
Tue Dec 31 23:00:00 EST 1974
· Atomkernenergie, v. 25, no. 2, pp. 115-124
·
OSTI ID:4120812
Related Subjects
*PEBBLE BED REACTORS-- TEMPERATURE DISTRIBUTION
210300* --Nuclear Power Plants--Power Reactors
Non- Breeding
Graphite Moderated
ACCURACY
AVR REACTOR
BURNUP
COMPUTER CALCULATIONS
CONFIGURATION CONTROL
D CODES
ERRORS
FLOW MODELS
GAS FLOW
HEAT TRANSFER
N77300* --Reactors--Power Reactors
Non-breeding
Graphite Moderated
POWER DENSITY
REACTOR CORES
REACTOR FUELING
SPATIAL DISTRIBUTION
VERY HIGH TEMPERATURE
210300* --Nuclear Power Plants--Power Reactors
Non- Breeding
Graphite Moderated
ACCURACY
AVR REACTOR
BURNUP
COMPUTER CALCULATIONS
CONFIGURATION CONTROL
D CODES
ERRORS
FLOW MODELS
GAS FLOW
HEAT TRANSFER
N77300* --Reactors--Power Reactors
Non-breeding
Graphite Moderated
POWER DENSITY
REACTOR CORES
REACTOR FUELING
SPATIAL DISTRIBUTION
VERY HIGH TEMPERATURE