DocumentCode :
2932767
Title :
Calculation of kinetic parameters of Caliban metallic core experimental reactor from stochastic neutron measurements
Author :
Casoli, Pierre ; Authier, Nicolas ; Baud, Jérémie
Author_Institution :
Centre de Valduc, Commissariat a l´´Energie Atomique, Is-sur-Tille, France
fYear :
2009
fDate :
7-10 June 2009
Firstpage :
1
Lastpage :
7
Abstract :
Several experimental devices are operated by the Criticality and Neutron Science Research Department of the CEA Valduc Laboratory. One of these is the metallic core reactor Caliban. Knowing the fundamental kinetic parameters of the reactor is very useful, indeed necessary, to the operator. The purpose of this study was to develop and perform experiments allowing to determinate some of these parameters. The prompt neutron decay constant and particularly its value at criticality can be measured with reactor noise techniques such as the interval-distribution, the Feynman variance-to-mean, and the Rossi-α methods. By introducing the Nelson number, the effective delayed neutron fraction and the average neutron lifetime can also be calculated with the Rossi-α method. Subcritical, critical, and even supercritical experiments were performed. With the Rossi-α technique, it was found that the prompt neutron decay constant at criticality was 6.02 × 105 ± 9%. Experiments also brought out the limitations of the used experimental parameters.
Keywords :
fission reactor kinetics; fission reactor monitoring; neutron detection; nuclear criticality safety; stochastic processes; CEA Valduc Laboratory; Caliban metallic core experimental reactor; Criticality and Neutron Science Research Department; Feynman variance-to-mean; Nelson number; Rossi-α methods; average neutron lifetime; criticality; effective delayed neutron fraction; prompt neutron decay constant; reactor kinetic parameters; reactor noise technique; stochastic neutron measurements; Atomic measurements; Delay effects; Inductors; Kinetic theory; Laboratories; Neutrons; Noise measurement; Particle measurements; Radioactive materials; Stochastic processes; Metallic Core Reactor; Nuclear Reactor Kinetic Parameters; Stochastic Neutron Measurements;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on
Conference_Location :
Marseille
Print_ISBN :
978-1-4244-5207-1
Electronic_ISBN :
978-1-4244-5208-8
Type :
conf
DOI :
10.1109/ANIMMA.2009.5503825
Filename :
5503825
Link To Document :
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