Abstract

The energy released from the nuclear fission process drives thermal expansion and mechanical interactions in nuclear reactors. These phenomena cause changes in the neutron chain reaction which results in further changes in thermal expansion and mechanical interactions. Coupling finite element analysis with Monte Carlo neutron transport analysis provides a pathway to simulate the thermal expansion and mechanical interaction to determine a fundamental parameter, namely, thermal expansion temperature coefficient of reactivity. Knowing the coefficient value allows predictions of how a reactor will behave under transient conditions. Using the coupling of finite element analysis and Monte Carlo neutron transport analysis, the thermal expansion temperature coefficient of reactivity was determined for the Godiva-IV reactor (−2E−05 Δk/k/°C) and the Experimental Breeder Reactor-II (EBR-II) (−1.4E−03 $/°C). The Godiva-IV result is within 3% of the measured result. The thermal expansion and mechanical interactions within EBR-II are sufficiently complex that experimentally measuring the isolated coefficient of reactivity was not possible. However, the calculated result fits well with the integral EBR-II reactivity coefficient measurements. Coupling finite element analysis with Monte Carlo neutron transport analysis provides a powerful technique that gives reactor operators and designers greater confidence in reactor operating characteristics and safety margins.

Highlights

  • Nuclear reactors exhibit remarkably complicated behavior originating from the energy released through the nuclear fission process

  • The results demonstrate that a coupling method of finite element analysis (FEA) and Monte Carlo Neutron Transport has to be potential to accurately predict the temperature coefficient

  • The energy released from the nuclear fission process drives complicated thermal expansion and mechanical interactions in nuclear reactors

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Summary

Introduction

Nuclear reactors exhibit remarkably complicated behavior originating from the energy released through the nuclear fission process. The complicated behavior involves many phenomena including nuclear, thermal, and mechanical. These phenomena involve processes that are challenging to quantify, measure, and model. When interactions between these phenomena are considered, Finite Element Methods and Their Applications the quantification, measurement, and modeling challenges become daunting. This chapter describes finite element analysis (FEA) coupled with Monte Carlo analysis as a methodology for quantification of a important nuclear parameter which is primarily influenced by thermal and mechanical phenomena present in nuclear reactors

Background
Godiva-IV and Experimental Breeder Reactor-II
Method
Finite element analysis
Mesh size
Boundary conditions
Timesteps
Monte Carlo neutron transport
FEA interface to neutron transport code
Quasi-static snapshots
Temperature coefficient calculations
A simple example
Godiva-IV
Thermal analysis
Structural analysis
Neutron transport
EBR-II
Findings
Conclusions

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