Chapter 1 Flashcards

1
Q

What is the typical temperature of a PWR?

A

300 C

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2
Q

Where are the control rods in the PWR?

A

Up

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3
Q

What are the control rods in the BWR?

A

Down

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4
Q

What happens to a material during irradiation?

A

Creation of new isotopes, swelling, radiation hardening, and embrittlement, phase changes.

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5
Q

Name some phenomena of fuel behaviour.

A

Pellet-Cladding Interaction (chemical and mechanical), Porosity Zones, affects conductivity, rim structure (high Pu), energetic fuel fragmentation (in fast transients)

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6
Q

What percentage qualify as moderate and large swelling?

A

Moderate 1-5%

Large > 10%

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7
Q

How is irradiated RPV embrittlement manifested?

A

Transition Temperature Increases and Upper Shelf Energy Decreases

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8
Q

What does the Transition Temperature depends on?

A

Combination of metallurgical (microstructure, heat treatment) and environmental variables (flux, fluence, Temperature)

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9
Q

What are the three main outcoming “particles” in a displacement collision?

A

Collision atom (decrease energy), gamma alpha or proton particle, and primary recoil atom (PRA).

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10
Q

What is the average energy of a fusion and a fusion PRA?

A

10 Kev and 50 kev

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11
Q

What are the primary displacement defects?

A

Vacancies = Self-Interstitials Atoms (SIA)

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12
Q

Describe the events following particle-atom collilsion (displacement in cascades)?

A

After collision, we create and diffuse V&SIA (and possible impurities). The outcome is either (1) V&I Recombination which leads to recombination, (2) V&I clustering which leads to formation of bubbles, loops and voids), (3) V&I Absorption at sinks (dislocations and clusters). 2 and 3 lead to damage accumulation and therefore change in dimensional and mechanical properties.

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13
Q

Why are the # of vacancies and the # of interestitials not equal after some time?

A

Dislocation sink is biased for Interstitials

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14
Q

Why is diffusion enhanced in irradiation?

A

Vacancy/SIA supersaturation, and since Interstitials are absrobed more rapidly there are a lot of vacancies which enhance diffusion.

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15
Q

Is steel an alloy or a composite?

A

Composite

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16
Q

What is the pressure in a PWR?

A

15 MPa

17
Q

What is the pressure at a BWR?

A

7 MPa

18
Q

What type of alloy is the RPV made off?

A

309 and 309 SS Alloy Steel

19
Q

What material is the control rods in the PWR made of?

A

B4C interior, and stainless steel cladding

20
Q

What is the fuel cladding made of?

A

Zr-Alloys

21
Q

What material issues does the fuel suffer?

A

fission gas release, FP swelling, thermal conductivity decrease with burnup

22
Q

What material issues does the cladding suffer?

A

Waterside corrosion and hydriding, embrittlement, growth, pellet-cladding interaction, creep, fretting

23
Q

What material issues does the neutron absorbers suffer?

A

embrittlement, thermal-mechanical fatigue

24
Q

What material issues does the RPV suffer?

A

radiation embirttlement

25
Q

What material issues does reactor internals suffer?

A

swelling/creep, stres-corrosion cracking, fatigue