Nuclear Reactor Material Annealing via Staged Thermal Treatment

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Solution Overview

Problem

Nuclear fission reactor materials, particularly components of reactor cores and fuel assemblies, experience radiation damage due to neutron exposure, leading to degradation and increased ductile-to-brittle transition temperatures, which existing methods struggle to effectively anneal and restore.

Innovation Solution

The implementation of annealing methods that involve determining specific temperature ranges based on radiation exposure, operating history, and material properties to heat components above their operating temperatures, allowing for the relief of stress and migration of crystalline defects, thereby relieving radiation damage, and subsequent cooling and tempering to lock in desired metallurgical qualities.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Reliability

If existing annealing methods are used on nuclear fission reactor materials, then some restoration may occur, but radiation damage cannot be effectively removed and ductile-to-brittle transition temperatures remain elevated

Engineering Contradiction:
Improveradiation damage removal effectivenessVSAvoidmaterial restoration capability
Core Design Contradiction:
ReliabilityVSEase of repair

Solution Approach 1:

The patent applies parameter changes by implementing a multi-stage thermal process with specific temperature ranges (first stage: 200-400°C, second stage: 400-600°C, third stage: 600-800°C) and controlled cooling rates (10-100°C/hour). These parameter variations enable progressive defect migration and annihilation that conventional single-stage annealing cannot achieve, effectively removing radiation damage while restoring material properties.

Inventive Principle:
Principle #35Parameter changes

Solution Approach 2:

The patent employs preliminary action through the first annealing stage at lower temperatures (200-400°C) before proceeding to higher temperatures. This preliminary stage prepares the material structure by initiating defect migration and reducing initial stress, making subsequent high-temperature treatment more effective and preventing structural degradation that would occur with direct high-temperature exposure.

Inventive Principle:
Principle #10Preliminary action

2Reliability

If high temperatures are used to anneal reactor materials, then defect migration and stress relief improve, but structural degradation and creep increase

Engineering Contradiction:
Improvedefect migration effectivenessVSAvoidstructural integrity
Core Design Contradiction:
ReliabilityVSStability of the object's composition

Solution Approach 1:

The patent uses preliminary action by implementing progressive temperature stages, starting with lower temperatures (200-400°C) to initiate defect migration and stress relief before gradually increasing to higher temperatures (600-800°C). This staged approach allows the material structure to adapt progressively, achieving effective defect removal while preventing sudden structural degradation that would occur with direct high-temperature treatment.

Inventive Principle:
Principle #10Preliminary action

Solution Approach 2:

The patent applies dynamics through controlled, gradual temperature increases and regulated cooling rates (10-100°C/hour). This dynamic thermal profile allows the material to continuously adapt its structure during heating and cooling, optimizing defect migration at each temperature stage while maintaining structural integrity through controlled thermal stress management.

Inventive Principle:
Principle #15Dynamics

3Productivity

If rapid cooling is applied after annealing, then time efficiency improves, but metallurgical quality and desired material properties are compromised

Engineering Contradiction:
Improveannealing process speedVSAvoidmetallurgical quality
Core Design Contradiction:
ProductivityVSManufacturing precision

Solution Approach 1:

The patent applies dynamics through controlled cooling rates (10-100°C/hour) that can be adjusted based on material thickness, initial temperature, and desired properties. This dynamic cooling approach optimizes the balance between productivity and metallurgical quality by allowing sufficient time for proper microstructure development while preventing excessive cooling times that would reduce operational efficiency.

Inventive Principle:
Principle #15Dynamics

Solution Approach 2:

The patent uses parameter changes by implementing a regulated cooling phase with specific rate ranges after the annealing stages. This controlled parameter change from high temperature to ambient conditions ensures proper metallurgical transformation and property development, achieving high-quality results while maintaining reasonable process throughput through optimized cooling rate selection.

Inventive Principle:
Principle #35Parameter changes

Applied Scientific Principles

This section explains which scientific principles are used to turn an abstract innovation direction into a practical engineering solution.

Function Achieved in This Case

This approach effectively removes radiation damage by thermally inducing the migration of defects to grain boundaries, relieving stress and improving the metallurgical qualities of reactor materials, while also considering safety margins and creep rates to prevent structural degradation.

Implementation Method 1

thermally inducing the migration of defects to grain boundaries

Methodology Applied
Scientific EffectThermal diffusion: Diffusion

Implementation Method 2

annealing methods that involve determining specific temperature ranges based on radiation exposure, operating history, and material properties to heat components above their operating temperatures, allowing for the relief of stress and migration of crystalline defects

Methodology Applied
Scientific EffectAnnealing: Annealing

Implementation Method 3

subsequent cooling and tempering to lock in desired metallurgical qualities

Methodology Applied
Scientific EffectPhase transformation: Phase Change

Data Source

PatentUS9011613B2System and method for annealing nuclear fission reactor materials
Publication Date: 2015.04.21 TERRAPOWER LLC
  • US9011613B2 patent drawing
  • US9011613B2 patent drawing
  • US9011613B2 patent drawing

AI summary

Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials.