Nuclear Fuel Rod Cladding Defect Management via Sub-cooling

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Solution Overview

Problem

Primary defects in nuclear fuel rods can lead to secondary degradation due to hydrogen absorption by the cladding, causing mechanical property deterioration and potential crack initiation, which existing methods partially address by reducing reactor power and increasing free volume but with limitations in gas mixing and steam penetration.

Innovation Solution

The method involves operating the reactor at reduced power and increased sub-cooling to enhance gas communication paths and mix hydrogen and steam homogeneously within the fuel rod, using a hydrogen-absorbing element in the plenums to mitigate hydriding, and strategically displacing control rods to identify and manage defect fuel rods, thereby reducing the risk of secondary defects.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Reliability

If reactor power is reduced to increase free volume and promote gas mixing, then hydrogen distribution becomes more homogeneous and secondary defect risk decreases, but reactor productivity and energy output are reduced

Engineering Contradiction:
Improvefuel rod integrityVSAvoidreactor power output
Core Design Contradiction:
ReliabilityVSProductivity

Solution Approach 1:

The patent applies preliminary action by implementing a specific operational procedure immediately after defect detection: reducing reactor power to 70-85% and increasing sub-cooling to 15-25K within a defined time frame (2-48 hours). This preliminary intervention creates optimal conditions for homogeneous hydrogen distribution before secondary defects can develop, thereby preventing future failures while temporarily reducing power output.

Inventive Principle:
Principle #10Preliminary action

Solution Approach 2:

The patent utilizes parameter changes by modifying key operational parameters (reactor power level and sub-cooling degree) to transform the internal environment of fuel rods. By adjusting these parameters, the free volume increases and gas mixing is enhanced, converting a potentially harmful situation into a controlled state that promotes hydrogen homogenization without complete shutdown.

Inventive Principle:
Principle #35Parameter changes

2Stability of the object's composition

If control rods are inserted to reduce power and increase free volume, then gas communication paths are enhanced and steam penetration is improved, but reactor power and energy production decrease

Engineering Contradiction:
Improvegas distribution homogeneityVSAvoidreactor power
Core Design Contradiction:
Stability of the object's compositionVSPower

Solution Approach 1:

The patent implements feedback by continuously monitoring reactor operation and adjusting control rod positions based on detected defect conditions. The system responds to the presence of primary defects by dynamically modifying power levels and control rod insertion depth, creating a closed-loop control mechanism that maintains optimal conditions for hydrogen mixing while minimizing impact on overall reactor power.

Inventive Principle:
Principle #23Feedback

3Strength

If the reactor is operated at reduced power for an extended period to allow homogeneous hydrogen distribution, then cladding mechanical properties are preserved, but operational time and productivity are reduced

Engineering Contradiction:
Improvecladding mechanical strengthVSAvoidoperational duration
Core Design Contradiction:
StrengthVSDuration of action of moving object

Solution Approach 1:

The patent applies partial action by implementing a moderate power reduction (70-85% of full power) rather than complete shutdown. This partial reduction is sufficient to achieve the critical goal of homogeneous hydrogen distribution and prevent secondary defects, while avoiding the excessive loss of operational time that would result from full reactor shutdown or more aggressive power reductions.

Inventive Principle:
Principle #16Partial or excessive action

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 reduces the risk of secondary defects by promoting homogeneous hydrogen distribution and reducing mechanical stress on the cladding, allowing for extended operation without additional shutdowns and maintaining reactor stability.

Implementation Method 1

a coolant flow through the core in contact with the fuel rods

Methodology Applied
Scientific EffectThermal conduction: Conduction (thermal)

Implementation Method 2

the reactor coolant is re-circulated as a coolant flow through the core

Methodology Applied
Scientific EffectConvection: Convection

Implementation Method 3

nuclear fuel in the form of fuel pellets enclosed in an inner space formed by the cladding

Methodology Applied
Scientific EffectNuclear fission: Nuclear Fission

Implementation Method 4

the inner side of the cladding is inclined to absorb hydrogen, so called hydriding

Methodology Applied
Scientific EffectAbsorption: Absorption (physical)

Data Source

PatentUS8477899B2Method for operating a reactor of a nuclear plant
Publication Date: 2013.07.02 WESTINGHOUSE ELECTRIC SWEDEN AB
  • US8477899B2 patent drawing
  • US8477899B2 patent drawing
  • US8477899B2 patent drawing

AI summary

A method of operating a nuclear reactor is disclosed. The reactor (1) encloses a core having a plurality of fuel rods (9). Each fuel rod (9) includes a cladding and fuel pellets of a nuclear fuel. The fuel pellets are arranged in an inner space of the cladding leaving a free volume comprising an upper plenum, a lower plenum and a pellet-cladding gap. The reactor is operated at a normal power and a normal inlet sub-cooling during a normal state. The reactor is monitored for detecting a defect on the cladding of any of the fuel rods. The operation of the reactor is changed to a particular state after detecting such a defect. The particular state permits an increase of the free volume in the defect fuel rod. The reactor is operated at the particular state during a limited time period, after which the reactor is operated at the normal state.