Zirconium Alloy Cladding and Cr2O3 Pellets for PCI Resistance

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Solution Overview

Problem

Nuclear reactors with zirconium-based fuel rods experience high stress and risk of cladding fracture due to Pellet Cladding Interaction (PCI) during transient power occurrences, limiting operational flexibility.

Innovation Solution

A method for operating nuclear reactors using fuel rods with a completely recrystallized zirconium-based alloy and uranium oxide pellets doped with chromium oxide (Cr2O3) to enhance thermal creep and reduce mechanical stress, controlling linear power density and variation to specific limits to prevent cladding damage.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Reliability

If conventional zirconium-based fuel rods are used, then the reactor structure is simple and manufacturing is easy, but the cladding is highly susceptible to PCI-induced fracture during transient power occurrences

Engineering Contradiction:
Improvecladding resistance to PCI fractureVSAvoidfuel rod composition complexity
Core Design Contradiction:
ReliabilityVSDevice complexity

Solution Approach 1:

The patent employs a composite material approach by combining zirconium alloy cladding with specific alloying elements (niobium at 0.8-1.3%, oxygen at 1000-1700 ppm, and controlled impurities) to create a material with enhanced resistance to PCI-induced fracture. This composite composition allows the cladding to withstand the mechanical and chemical stresses during transient power occurrences while maintaining structural integrity.

Inventive Principle:
Principle #40Composite materials

Solution Approach 2:

The patent applies parameter changes by precisely controlling the chemical composition parameters of the zirconium alloy, specifically the niobium content (0.8-1.3%), oxygen content (1000-1700 ppm), and impurity levels. These parameter optimizations transform the cladding's mechanical properties, enhancing its creep resistance and fracture toughness without excessive complexity in the manufacturing process.

Inventive Principle:
Principle #35Parameter changes

2Reliability

If Cr2O3 is added to fuel pellets to promote thermal creep, then PCI resistance is improved, but the operational flexibility of the reactor remains insufficient

Engineering Contradiction:
ImprovePCI resistanceVSAvoidoperational flexibility
Core Design Contradiction:
ReliabilityVSAdaptability or versatility

Solution Approach 1:

The patent changes the operational parameters by defining specific limits for linear power density and its variation during transient power occurrences. These parameter controls allow the reactor to operate with enhanced flexibility while maintaining improved PCI resistance through the combined effect of Cr2O3-doped pellets and optimized zirconium alloy cladding.

Inventive Principle:
Principle #35Parameter changes

Solution Approach 2:

The patent applies preliminary action by pre-doping the fuel pellets with Cr2O3 during manufacturing, which establishes enhanced thermal creep properties before the reactor operates. This preliminary modification to the fuel pellets ensures that the material is pre-conditioned to resist PCI effects, thereby improving reliability without restricting operational flexibility.

Inventive Principle:
Principle #10Preliminary action

3Adaptability or versatility

If the linear power density limit is set high, then operational flexibility is improved, but the risk of exceeding elastic limit and causing cladding damage increases

Engineering Contradiction:
Improveoperational flexibilityVSAvoidcladding stress and fracture risk
Core Design Contradiction:
Adaptability or versatilityVSObject-affected harmful factors

Solution Approach 1:

The patent changes the material parameters of the cladding through optimized alloy composition, which increases its elastic limit and stress-bearing capacity. This allows the reactor to operate at higher linear power density limits with reduced risk of cladding damage, thereby improving operational flexibility without proportionally increasing the harmful effects of cladding stress.

Inventive Principle:
Principle #35Parameter changes

Solution Approach 2:

The patent applies beforehand cushioning by incorporating Cr2O3 into the fuel pellets, which promotes thermal creep and reduces mechanical stress on the cladding before transient power occurrences happen. This preventive measure cushions the cladding against excessive stress during high power density operations, allowing higher operational limits without proportionally increasing fracture risk.

Inventive Principle:
Principle #11Beforehand cushioning (Prior cushioning)

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

The method significantly increases the resistance of fuel rods to PCI, allowing for more flexible reactor operation by reducing mechanical and chemical stress on the cladding, thereby enhancing the reactor's ability to withstand transient power events without fracturing.

Implementation Method 1

the use of chromium oxide Cr2O3 as an additive in fuel pellets in order to promote the thermal creep thereof and limit the risks of the cladding becoming damaged owing to the phenomenon of pellet cladding interaction (PCI)

Methodology Applied
Scientific EffectThermal creep: Creep

Implementation Method 2

This rapid increase of power brings about significant expansion of the pellets. Since the thermal expansion of the pellets is greater than that of the cladding, the cladding is consequently placed in a state of traction by the pellets

Methodology Applied
Scientific EffectThermal expansion: Thermal Expansion

Implementation Method 3

These stresses progressively relax by means of creeping

Methodology Applied
Scientific EffectCreeping: Creep

Data Source

PatentUS9378850B2Method for operating a nuclear reactor and use of a specific fuel rod cladding alloy in order to reduce damage caused by pellet/cladding interaction
Publication Date: 2016.06.28 AREVA NP SAS
  • US9378850B2 patent drawing
  • US9378850B2 patent drawing
  • US9378850B2 patent drawing

AI summary

A method for operating a nuclear reactor in order to produce electricity, such that the reactor is controlled so that, during a transient power occurrence for at least one of: a linear power density of the nuclear fuel rod remains lower than a limit linear power density, the limit linear power density being greater than 430 W/cm, and a variation of linear power density of the nuclear fuel rod remains lower than a limit variation, the limit variation being greater than 180 W/cm.