A model of heat transfer dynamics of coupled multiphase-flow and neutron-radiation: Application to a nuclear fluidized bed reactor

Christopher C. Pain (Corresponding Author), Jefferson L.M.A. Gomes, Matthew D. Eaton, Cassiano R.E. de Oliveira, Anthony J.H. Goddard

Research output: Contribution to journalArticle

9 Citations (Scopus)

Abstract

Purpose – To present dynamical analysis of axisymmetric and three-dimensional (3D) simulations of a nuclear fluidized bed reactor. Also to determine the root cause of reactor power fluctuations.

Design/methodology/approach – We have used a coupled neutron radiation (in full phase space) and high resolution multiphase gas-solid Eulerian-Eulerian model.

Findings – The reactor can take over 5?min after start up to establish a quasi-steady-state and the mechanism for the long term oscillations of power have been established as a heat loss/generation mechanism. There is a clear need to parameterize the temperature of the reactor and, therefore, its power output for a given fissile mass or reactivity. The fission-power fluctuates by an order of magnitude with a frequency of 0.5-2?Hz. However, the thermal power output from gases is fairly steady.

Research limitation/implications – The applications demonstrate that a simple surrogate of a complex model of a nuclear fluidised bed can have a predictive ability and has similar statistics to the more complex model.

Practical implications – This work can be used to analyze chaotic systems and also how the power is sensitive to fluctuations in key regions of the reactor.

Originality/value – The work presents the first 3D model of a nuclear fluidised bed reactor and demonstrates the value of numerical methods for modelling new and existing nuclear reactors.
Original languageEnglish
Pages (from-to)765-807
Number of pages43
JournalInternational Journal of Numerical Methods for Heat & Fluid Flow
Volume15
Issue number8
DOIs
Publication statusPublished - 2005

Fingerprint

Fluidized Bed
Multiphase Flow
Multiphase flow
Neutron
Fluidized beds
Reactor
Heat Transfer
Neutrons
Radiation
Heat transfer
Chaotic systems
Nuclear reactors
Heat losses
Gases
Model
Fluctuations
Numerical methods
Nuclear Reactor
Parameterise
Output

Keywords

  • flow
  • heat transfer
  • nuclear reactors
  • numerical analysis

Cite this

A model of heat transfer dynamics of coupled multiphase-flow and neutron-radiation : Application to a nuclear fluidized bed reactor. / Pain, Christopher C. (Corresponding Author); Gomes, Jefferson L.M.A.; Eaton, Matthew D.; de Oliveira, Cassiano R.E.; Goddard, Anthony J.H.

In: International Journal of Numerical Methods for Heat & Fluid Flow, Vol. 15, No. 8, 2005, p. 765-807.

Research output: Contribution to journalArticle

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AB - Purpose – To present dynamical analysis of axisymmetric and three-dimensional (3D) simulations of a nuclear fluidized bed reactor. Also to determine the root cause of reactor power fluctuations.Design/methodology/approach – We have used a coupled neutron radiation (in full phase space) and high resolution multiphase gas-solid Eulerian-Eulerian model.Findings – The reactor can take over 5?min after start up to establish a quasi-steady-state and the mechanism for the long term oscillations of power have been established as a heat loss/generation mechanism. There is a clear need to parameterize the temperature of the reactor and, therefore, its power output for a given fissile mass or reactivity. The fission-power fluctuates by an order of magnitude with a frequency of 0.5-2?Hz. However, the thermal power output from gases is fairly steady.Research limitation/implications – The applications demonstrate that a simple surrogate of a complex model of a nuclear fluidised bed can have a predictive ability and has similar statistics to the more complex model.Practical implications – This work can be used to analyze chaotic systems and also how the power is sensitive to fluctuations in key regions of the reactor.Originality/value – The work presents the first 3D model of a nuclear fluidised bed reactor and demonstrates the value of numerical methods for modelling new and existing nuclear reactors.

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