Modeling for fuel element deformation

Patent metadata

Field	Value
Publication number	US-10163534-B2
Application number	US-201514605831-A
Country	US
Kind code	B2
Filing date	Jan 26, 2015
Priority date	Jan 27, 2014
Publication date	Dec 25, 2018
Grant date	Dec 25, 2018

Abstract

A computerized system for modeling reactor fuel element and fuel design to determine the thermo-mechanical performance thereof includes a processor coupled to memory, the memory configuring the processor to execute a fuel element analysis and an output configured to communicate data that describes the thermo-mechanical performance of the fuel element and fuel design based on the fuel element performance analysis. The processor is configured to estimate the mechanical behavior of a fuel by creating separate variables for the open and closed porosity components, conducting a routine for the open and closed porosity components that processes the current state of the fuel and updates the current state and forces of each of the open and closed porosity components, and combining the updates for the current state and forces according to a weighting; and estimate the creep and swelling behavior of a cladding.

First claim

What is claimed is:

1. A computerized system for modeling reactor fuel element and fuel design to determine the thermo-mechanical performance thereof, comprising:
a processor coupled to memory, the memory configuring the processor to execute a fuel element performance analysis, the processor configured to:
estimate a mechanical behavior of a model of a fuel element having open porosity and closed porosity components by (a) creating separate variables, within the model, for the open porosity and the closed porosity components of the fuel element, (b) conducting a computer-based simulation for both the open porosity and the closed porosity components that processes a current state of the model of the fuel element and generates one or more updates associated with the current state of the model including forces of each of the open porosity and the closed porosity components of the model, and (c) combining the one or more updates for the current state of the model including the forces acting on the model of the fuel element from the processing of the open porosity and the closed porosity components according to a weighting between the open porosity and closed porosity components; and
estimate a creep and a swelling behavior of a model of a cladding of the fuel element, the model of the cladding including estimated parameters wherein the estimated parameters are utilized in the fuel element performance analysis;

an output that communicates data that describes the thermo-mechanical performance of the reactor fuel element and fuel design based on the fuel element performance analysis;
a communications interface that sends, to a reactor controller, at least a portion of the data that describes the thermo-mechanical performance of the reactor fuel element and fuel design based on the fuel element performance analysis; and

the reactor controller that controls an operating nuclear reactor based on the at least a portion of the data.

2. The computerized system of claim 1 , wherein the mechanical behavior of the model of the fuel element is estimated utilizing a model that accounts for the constitutive behavior of the fuel element with the open porosity and the closed porosity components.

3. The computerized system of claim 1 , wherein the weighting is governed by a fission gas release parameter.

4. The computerized system of claim 1 , wherein a supervisory routine of the system builds a stiffness matrix describing stiffness parameters for every element of the fuel element performance analysis.

5. The computerized system of claim 4 , wherein the processor is configured to conduct the estimate of the mechanical behavior of the model of the fuel element for each element of the fuel element performance analysis.

6. The computerized system of claim 5 , wherein the computer-based simulation for processing the current state of the fuel element creates an estimate of a local stress tensor at the end of a time increment, defines a strain rate tensor and its derivatives, and estimates porosity and its derivatives.

7. The computerized system of claim 6 , wherein the estimate of the local stress tensor at the end of the time increment and the defined strain rate tensor and porosity parameters are estimated within an implicit method or an explicit method to determine changes in fuel parameters over the time increment.

8. The computerized system of claim 7 , wherein the determined changes are utilized to form a Jacobian matrix of a model, and wherein at least one of the Jacobian matrix, the updated stresses, and updated state variables are returned for the weighted combination.

9. The computerized system of claim 1 , wherein the creep and the swelling behavior of the cladding is calculated by summing the contributing strain rates associated with a plurality of deformation parameters.

10. The computerized system of claim 1 , wherein the reactor fuel element and fuel design is altered based on fuel element performance data from the fuel element performance analysis indicating a design constraint has not been met.

11. The computerized system of claim 1 , wherein the processor is configured to receive fuel element operating data regarding the fuel element, wherein the processor determines the fuel element needs to be replaced, removed, repaired, or shuffled based on the fuel element operating data.

12. The computerized system of claim 11 , wherein the processor is configured to determine fuel element performance data based on the fuel element operating data, wherein the fuel element performance data includes an indication of an amount of additional energy that is able to be extracted from the fuel element.

13. A computerized method for modeling reactor fuel element and fuel design to determine the thermo-mechanical performance thereof, comprising:
estimating (a) a mechanical behavior of a model of a fuel element, and (b) a creep and a swelling behavior of a model of a cladding;
passing estimated parameters to a fuel element performance analysis for modeling the reactor fuel element and fuel design;
wherein the estimate of the mechanical behavior of the model of the fuel element comprises:
creating, within the model of the fuel element, separate variables for open porosity and closed porosity components of the fuel element,
conducting a computer-based simulation for both the open porosity and the closed porosity components of the model of the fuel element that processes a current state of the model of the fuel element and generates one or more updates associated with the current state including forces of each of the open porosity and the closed porosity components of the fuel element, and
combining the one or more updates for the current state including the forces of the fuel element from the processing of the open porosity and the closed porosity components according to a weighting, wherein the combined state and forces of the fuel element are calculated;

the method further comprising:
communicating data that describes the thermo-mechanical performance of the reactor fuel element and fuel design based on the fuel element performance analysis;
communicating, to a reactor controller, at least a portion of the data that describes the thermo-mechanical performance of the reactor fuel element and fuel design based on the fuel element performance analysis; and

controlling, by the reactor controller, an operating nuclear reactor based on the at least a portion of the data.

14. The computerized method of claim 13 , further comprising building a stiffness matrix describing stiffness parameters for every element of the fuel element performance analysis.

15. The computerized method of claim 14 , further comprising conducting the estimate of the mechanical behavior of the model of the fuel element for each element of the fuel element performance analysis, wherein the fuel element performance analysis is a finite element analysis.

16. The computerized method of claim 13 , wherein the weighting is governed by a fission gas release parameter.

17. The computerized method of claim 13 , wherein the computer-based simulation for processing the current state of the fuel element creates an estimate of a local stress tensor at the end of a time increment, defines a strain rate tensor and its derivatives, and estimates porosity and its derivatives.

18. The computerized method of claim 17 , wherein the estimate of the local stress tensor at the end of the time increment and the defined strain rate tensor and porosity parameters are estimated within an implicit method or an explicit method to deter

Assignees

• Terrapower Llc

Inventors

• Hackett Micah
• Latta Ryan
• Miller Samuel J
• Povirk Gary
• Werner Mark R
• Xu Cheng

Classifications

• G21D3/001 Primary

  Computer implemented control · CPC title

• G21C3/06 Primary

  Casings; Jackets · CPC title

• Y02E30/40

  Cross-Sectional Technologies · mapped topic

• G21C2003/045

  Physics · mapped topic

• G21C3/04

  Constructional details · CPC title