Title :
Application of the Modified Source Multiplication (MSM) technique to subcritical reactivity worth measurements in thermal and fast reactor systems
Author :
Blaise, Patrick ; Mellier, Frédéric ; Fougeras, Philippe
Author_Institution :
Reactor Phys. & Cycle Service (SPRC), CEA, St. Paul-lez-Durance, France
Abstract :
The Amplified Source Multiplication (ASM) method and its improved Modified Source Multiplication (MSM) method have been widely used in the CEA´s EOLE and MASURCA critical facilities over the past decades for the determination of reactivity worths by using fission chambers in subcritical configurations. They have been successfully applied to absorber (single or clusters) worth measurement in both thermal and fast spectra, or for (sodium or water) void reactivity worths. The ASM methodology, which is the basic technique to estimate a reactivity worth, uses relatively simple relationships between count rates of efficient miniature fission chambers located in slightly subcritical reference and perturbed configurations. If this method works quite well for small reactivity variation (a few effective delayed neutron fraction), its raw results needs to be corrected to take into account the flux perturbation in the fission chamber. This is performed by applying to the measurement a correction factor called MSM. Its characteristics is to take into account the local space and energy variation of the spectrum in the fission chamber, through standard perturbation theory applied to neutron transport calculation in the perturbed configuration. The proposed paper describes in details both methodologies, with their associated uncertainties. Applications on absorber cluster worth in the MISTRAL-4 full MOX mock-up core and the last core loaded in MASURCA show the importance of the MSM correction on raw data.
Keywords :
fission reactor safety; fission reactor theory; neutron transport theory; reactivity (fission reactors); MASURCA critical facility; MISTRAL-4; amplified source multiplication method; delayed neutron fraction; fast reactor system; fission chamber; full MOX mock-up core; modified source multiplication method; modified source multiplication technique; neutron transport calculation; standard perturbation theory; subcritical reactivity; thermal reactor system; Boron; Calibration; Delay effects; Density estimation robust algorithm; Detectors; Inductors; Kinetic theory; Neutrons; Performance evaluation; Physics; ASM; MSM; measurements; perturbation; subcritical;
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
DOI :
10.1109/ANIMMA.2009.5503677