Title :
Self Powered neutron detector based reactor flux estimation using multisensor particle filter
Author :
Tamboli, Prakash Kumar ; Duttagupta, Siddhartah P. ; Roy, Kallol
Author_Institution :
EE Dept., Indian Inst. of Technol., Mumbai, Mumbai, India
Abstract :
In this paper, we propose an improved method of In-core neutron flux estimation using Inconel Self Powered Neutron Detectors (SPNDs). The method proposed here is based upon multi-sensor based particle filter utilizing a number of uniformly distributed SPNDs along with the out-core ionization chambers which measure the overall flux. The proposed method estimates the neutron flux of large non-linear core volume involving stiff non-linearities with non-Gaussian uncertainties both in the process and sensor model. We propose an improved particle filtering based data fusion algorithm on multi-sensor network for flux estimation under nonlinear non-Gaussian environment. The nonlinear system in our study is a large core nuclear reactor measured through in-core Self Powered Neutron Detectors. Many critical applications such as reactor protection and control rely upon the neutron flux information and thus make the reliability of data an utmost important. The point kinetic model based on neutron transport theory conveniently explains the dynamics of nuclear reactor. The state equation in point kinetic model is stiff nonlinear set of equations. The neutron flux in the large core, loosely coupled reactor are sensed by multiple sensors measuring point fluxes located at various locations inside the reactor core. The flux values are coupled to each other through diffusion equation. The coupling facilitates redundancy in the information. The multiple independent information about the localized flux peaking can be fused together to enhance the estimation accuracy to a great extent. In our work, we establish, observation model for the neutron flux sensor used for large core flux measurement i.e. Self Powered Neutron Detectoric document.
Keywords :
fission reactor core control; fission reactor instrumentation; fission reactor kinetics; fission reactor safety; neutron detection; neutron transport theory; particle filtering (numerical methods); self-powered neutron detectors; sensor fusion; SPND; Self Powered Neutron Detectoric document; data fusion algorithm; data reliability; diffusion equation; flux estimation; in-core neutron flux estimation; loosely coupled reactor; multisensor network; multisensor particle filter; neutron flux; neutron flux information; neutron flux sensor; neutron transport theory; nonlinear core volume; nonlinear equations; nonlinear nonGaussian environment; nuclear reactor dynamics; out-core ionization chambers; point kinetic model; reactor core; reactor flux estimation; reactor protection; self powered neutron detector; Detectors; Estimation; Inductors; Mathematical model; Neutrons; Particle filters; neutron flux monitoring; particle filtering; point kinetic Equation; sensor network architecture;
Conference_Titel :
Physics and Technology of Sensors (ISPTS), 2015 2nd International Symposium on
Conference_Location :
Pune
DOI :
10.1109/ISPTS.2015.7220093