The Stochastic Point Reactor Equation with Thermal Feedback

Chen Dubi, Anil K. Prinja

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

Modeling and simulation of stochastic fission chains is central to the subject of reactor noise which has important practical applications in reactor control and measurements. One of the most classic works, modeling the stochastic fission chains in a reactor with thermal feedback is due to Harris (1958), where a discretization of the energy bins is preformed, to allow use of the Master equation technique. In the present study we will construct an Ito type SDE counterpart to the classic Harris model. In particular, we will start by defining the drift and the noise amplitude for each of the variables in the system. Then we will compute from first principles the covariance between the system variables, and finally, we will prove that the Harris model and the SDE model have a very strong common feature: they share the exact same second moment equations.

Original languageEnglish
Title of host publicationProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
PublisherAmerican Nuclear Society
Pages1996-2005
Number of pages10
ISBN (Electronic)9780894482229
DOIs
StatePublished - 1 Jan 2025
Externally publishedYes
Event2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025 - Denver, United States
Duration: 27 Apr 202530 Apr 2025

Publication series

NameProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025

Conference

Conference2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
Country/TerritoryUnited States
CityDenver
Period27/04/2530/04/25

Keywords

  • Master equation
  • Stochastic differential equations
  • Stochastic transport
  • diffusion scale approximation
  • thermal feedback

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Applied Mathematics

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