Failures of Nuclear Reactors Materials

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Discussion Overview

The discussion revolves around the failures of materials used in nuclear reactors, exploring various conditions and mechanisms that contribute to these failures. Participants touch on specific incidents, material behaviors under radiation, and procedural safeguards in reactor operations.

Discussion Character

  • Exploratory
  • Technical explanation
  • Debate/contested

Main Points Raised

  • Some participants note that materials in the Three Mile Island Unit 2 (TMI-2) incident melted under unusual conditions where normal heat transfer was disrupted.
  • Common failure mechanisms discussed include fatigue, normal corrosion, intergranular stress corrosion cracking (IGSCC), irradiation-assisted stress corrosion cracking (IASCC), and erosion/corrosion.
  • One participant mentions that overload failures are typically preceded by corrosion or fatigue mechanisms.
  • Another participant highlights that materials exposed to ionizing radiation or neutrons can undergo significant changes, affecting their brittleness and strength, which complicates material selection for components like valve diaphragms.
  • Increased ductile to brittle transition temperatures in iron metals subjected to neutron flux are noted, leading to different failure modes.
  • One participant discusses the procedural minimization of delayed hydride cracking (DHC) in Candu reactors by maintaining specific temperature ranges during operation.
  • Concerns about the 'creep' effect in pressurized tubes are reiterated, indicating potential operational challenges for nuclear plants.

Areas of Agreement / Disagreement

Participants express various viewpoints on the mechanisms of material failure and operational procedures, with no consensus reached on specific solutions or the implications of the discussed phenomena.

Contextual Notes

Some claims rely on specific procedural knowledge and may depend on particular reactor designs, which are not universally applicable. The discussion includes both technical and informal exchanges, with some posts diverging into humor.

Who May Find This Useful

Individuals interested in nuclear engineering, materials science, and reactor safety may find the insights shared in this discussion relevant.

M Usman
Please

Kindly porvide information about the failure of nuclear reactors materials
 
Engineering news on Phys.org
M Usman said:
Please
Kindly porvide information about the failure of nuclear reactors materials
Under what conditions?

Materials in TMI-2 melted, but that was under extremely unusual conditions where the normal heat transfer mechanism was removed.

Under normal circumstances, the main problems are fatigue, 'normal' corrosion, intergranular stress corrosion cracking (IGSCC), irradiation-assisted stress corrosion cracking (IASCC), and erosion/corrosion. I don't believe there has been any strain-to-failure, and overload failures are usually preceeded by one of the corrosion/fatigue mechanisms mentioned.

The Minerals, Metals & Materials Society (TMS) has a special symposium devoted to environmental degradation of nuclear materials - Environmental Degradation of Materials in Nuclear Systems-Water Reactors. If possible try to locate the proceedings of this conference - the 12th (August 2005) is mentioned here http://www.tms.org/Meetings/Specialty/ED2005/home.html
 
Many materials change when in sitting in ionizing radiation/neutrons for a while.

Many plastics will become more brittle, others will become softer. Soap based greases will become more fluid like. Oils will become more viscous and gummy. Rubber loses strength. Plexiglass, styrofoam, teflon, nylon: all this type of stuff is majorly effected.

This makes selecting materials such as valve diaphrams or plastic solenoid valve internals very important.

Ductile to brittle transition temp raises when iron metels are subjected to neutron flux, meaning although the metal gains a higher ultimate strength, when it fails it will fail more like ceramics than soft metal. Also 'creep' effect is increased (tubes under pressure will elongate). This can be a major irritation for nuke plants.
 
Homer Simpson said:
Also 'creep' effect is increased (tubes under pressure will elongate). This can be a major irritation for nuke plants.
As well as DHC, which hopefully today is not the problem it was.
 
For Candu's, probablility of DHC with the zirconium pressure tubes is minimized procedurally by moving through the 100-200 celsius range without delay on run up/run down. Above this temp the hyrogen goes into solution with the Zr, and as far as I understand, DHC will not occur. As well, it is shown that the pt's will leak before break, so early warning is seen, not to mention extensive inspection on shutdown. All this info is available publicly on the canteach.candu website, a great collection of info.
 
*chuckle*

Sorry, I just think it's really funny that the name "Homer Simpson" appears in a thread about failures of nuclear reactors. :smile:

Carry on...
 
Yeah, I had the same reaction. :biggrin:
 
It's pronounced 'nucular'. Nucular.
 
So, does that make you a nucular safety inspector, Homer?
 
  • #10
Nope, I can only aspire to that level of greatness. My job title is valve turner and ticky box checker. I am also skill broadened in the area of Sump Level Maintenance.
 
  • #11
Merry Christmas, Homer. I'm glad to see that you work at a nuclear power plant.

Happy New Year.
 
  • #12
Not sure if it's just a joke, but OUR Homer Simpson also lives in a place called Springfield.
 
  • #13
Merry Christmas and happy new year to You! Thanks.



BTW:

Not sure if it's just a joke, but OUR Homer Simpson also lives in a place called Springfield.

He's OUR Homer Simpson! Eh! :smile:
http://ccr.ptbcanadian.com/simpsons/
 
Last edited by a moderator:
  • #14
"OUR" meaning the Homer that frequents physicsforums of course.
 

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