lec 5 Flashcards

1
Q

list of guest smrs

A

✓ BWRX-300 reactor (GE Hitachi)
✓ Integrated molten salt reactor (Terrestrial Energy)
✓ Xe-100 (High temperature gas reactor) (X-Energy)
✓ Arc-100 (Sodium fast reactor) (Arc Technologies)
✓ e-Vinci (Heat pipe micro reactor) (Westinghouse Inc)

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2
Q

vdr processes (slide 6)

A
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3
Q

Licensing Vendor
Design Review

slide 8

A
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4
Q

Pre-Licensing
Vendor Design
Review – What
is it?

A

The reviews take place in three
phases, each of which is conducted
against related CNSC regulatory
documents and Canadian codes &
standards:
✓basically, use REGDOC 2.5.2

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5
Q

Design Reviews: Phase 1 def

A

Pre-Licensing Assessment of Compliance
with Regulatory Requirements:

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6
Q

Design Reviews: Phase 1

A

This phase involves an overall assessment of
the vendor’s nuclear power plant design against
the most recent CNSC design requirements for
new nuclear power plants in Canada
✓REGDOC-2.5.2,
✓And all other related CNSC regulatory documents and
Canadian codes & standards.

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7
Q

Design Reviews
Phase 2: def

A

Pre-Licensing Assessment for Any
Potential Fundamental Barriers to Licensing

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8
Q

Design Reviews
Phase 2:

A

✓This phase goes into further details with
a focus on
✓identifying any potential fundamental barriers
to licensing the vendor’s nuclear power plant
design in Canada.

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9
Q

Design Reviews:Phase 3: def

A

Follow-up

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10
Q

Design Reviews:Phase 3

A

✓This phase allows the vendor to follow-up on certain
aspects of Phase 2 findings by:
▪ seeking more information from the CNSC about a
Phase 2 topic; and/or
▪ asking the CNSC to review activities taken by the
vendor towards the reactor’s design readiness,
following the completion of Phase 2

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11
Q

R&D Challenges
Due to conceptual
FOAK Designs

A
  • Materials
    ✓Higher temperatures
    ✓Irradiation damage
  • Fuel
    ✓Modified designs need to be tested and
    qualified
  • Hydrogen production
    ✓Methods
    ✓Coupling to the plant
  • Thermal hydraulics and safety
  • Fuel cycles
  • Cross-cutting groups (fuel cycles, hydrogen,
    economic evaluation, safety, proliferation
    resistance) were formed within GenIV
    13
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12
Q

importance of SMRs

A

SMRs are flexible systems that can be
adapted for non-electric applications,
according to their key operating parameters,
i.e., exit working fluid temperature.
They can be integrated effectively into the energy systems supporting communities from
largest cities to most remote locations
Opportunity to support applications beyond solely electricity generation.

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13
Q

SMR designs and Technologies Around the World: slide 16

A
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14
Q

small modular Reactors (SMRs) Technology: selected designs

A

WATER COOLED SMALL MODULAR
REACTORS (LAND BASED)
* WATER COOLED SMALL MODULAR
REACTORS (MARINE BASED)
* HIGH TEMPERATURE GAS COOLED SMALL
MODULAR REACTORS
* FAST NEUTRON SPECTRUM SMALL
MODULAR REACTORS
* MOLTEN SALT SMALL MODULAR
REACTORS
* MICRO-SIZED SMALL MODULAR
REACTORS

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15
Q

slide 18-22

A
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16
Q

How is each SMR different from CANDU?

A

design
nuclear steam supply
main reactor systems
main reactor safety systems
containment
balance of plant
plant layout
economics

17
Q

How is each SMR different from CANDU? design

A

core design
fuel

18
Q

How is each SMR different from CANDU? nuclear steam supply

A

steam generator
heat transport system

19
Q

How is each SMR different from CANDU? main reactor systems

A

control systems
moderator
coolant
pressurizer

20
Q

How is each SMR different from CANDU? main reactor safety systems

A

shut of rods, poisons
emerg core cooling

21
Q

How is each SMR different from CANDU? balance of plant

A

turbine hall
generator
transformers

22
Q

How is each SMR different from CANDU? (slide 24)

A
  • Why did the engineers change the coolant?
    ✓ Why did they change the model/core?
    ✓ Is the core different?
    ✓ Why and how do you know?
  • Why did they change all these other things to
    satisfy achieving the 3 cs?
    ✓ Why would we change the fundamental things like the
    cooler
    ✓ What about if a reactor has only two Cs,
    ✓ Is this acceptable to the regulator?
  • What are the safety design features?
    ✓ What are the differences in the design features
  • Why do some have a smaller core?
    ✓ With a high energy density core
    ✓ Why no moderator.?
  • Cores with high energy density, because you
    got to cool very quickly.
    ✓ You don’t care about it being a good moderator
    because it’s a fast reactor
    *Well, this has a different the core is different.
    ✓You know, it might be a molten salt
    ✓What’s different about that?
    *Why how would we change the fundamental
    things like the cooler?
    ✓why would we?
    *What are the design features?
    ✓What are the reasons for the different design
    features?
    ✓Because you still have to have the three seats.
    *Designers have made different choices, or their
    reactor design, let’s understand the choices.
    ✓Why did they do what they do? And that, as I say,
    brings out for instance
23
Q
  • BWRX-300 intro
A

BWRX-300 is the simplest and
most innovative BWR design
* Built by General Electric-Hitachi
* 300 MW(e)
* Water-cooled
* Natural circulation SMR
* Utilizing simple, natural
phenomena driven safety
systems.
* 10th generation of the Boiling
Water Reactor (BWR)
* The design has been developed
with a strict adherence to a
philosophy which follows the
IAEA Defense-in-Depth guidelines.

24
Q

bwrx-300

A

WATER COOLED SMALL MODULAR
REACTORS (LAND BASED)
* BWRX-300 (GE-Hitachi Nuclear Energy, USA
and Hitachi-GE Nuclear Energy, Japan)
25
David Hinds, Engineering Technical Leader, GE Hitachi

25
Q

Xe-100

A
  • HIGH TEMPERATURE GAS COOLED
    SMALL MODULAR REACTORS
  • Xe-100 (X Energy, LLC, United States of
    America)
    27
  • Luke McSweeney, Lead Probabilistic Risk
    Assessment, X-Energy
26
Q

Xe-100 intro

A
  • The Xe-100 is a pebble bed reactor
  • It features a continuous refueling system
    with low enriched fuel spheres or
    pebbles of approximately 15.5 wt.%
  • Enters the top of the reactor and passing
    through the core six (6) times to achieve
    a final average burnup of 165 000 MWd /
    tHM
  • The reactor pressure vessel (RPV) and
    internal structures are designed for a 60-
    year life
27
Q

Arc-100

A
  • FAST NEUTRON SPECTRUM SMALL
    MODULAR REACTORS
  • ARC-100 (ARC Nuclear Canada, Inc., Canada)
    29
    https://www.arc-cleantech.com/3D-model/ARC%20September%202023/index.htm
    Cal Doucette - Director Of
    Engineering - ARC Clean Energy
28
Q

arc-100 into

A
  • Sodium-cooled, fast flux, pooltype reactor with metallic fuel
  • ARC-100 addresses the four
    challenges which limits public
    acceptance/expansion of nuclear
    ✓ Small size with affordable upfront cost
    ✓ liquid sodium coolant, its ‘fast’ neutrons have
    much more energy, giving it the capacity to
    be fueled with and recycle its own used fuel
    ✓ utilizes a metallic alloy of uranium instead of
    uranium oxide, foundation for its inherent,
    walk away safety.
    ✓ refuels once every 20 years. Replacement of
    the entire 20-year fuel cartridge for recycling
    reduces the risk of nuclear proliferation.
29
Q

IMSR

A
  • MOLTEN SALT SMALL MODULAR
    REACTORS
  • Integral Molten Salt Reactor
    (Terrestrial Energy Inc., Canada)
    31
    David Leblanc, President and CTO of Terrestrial Energy
30
Q

IMSR Intro

A
  • 440 megawatts-thermal molten salt
    fueled reactor
  • It features a completely sealed
    reactor vessel with integrated pumps,
    heat exchangers and shutdown rods
    all mounted inside a single vessel;
    ✓ The sealed core-unit is replaced
    completely at the end of its useful
    service life (nominally 7 years)
  • highest levels of inherent safety
    ✓ no dependence on operator intervention,
    powered mechanical components, coolant
    injection or their support systems such as
    electricity supply or instrument air in
    dealing with upset conditions
31
Q

E-Vinci heat Pipe Micro Reactor

A
  • MICRO SMALL MODULAR REACTORS
  • E-Vinci heat Pipe Micro Reactor
    (GE-Hitachi Nuclear Energy, USA and
    Hitachi-GE Nuclear Energy, Japan)
    33
    Dr. Grant Cherkas, Vice President, Market Development
    and Chief Engineer, Westinghouse Inc.
32
Q

E-Vinci heat Pipe Micro Reactor intro

A
  • Very Low Pressure
  • Passive safety
  • Single failure tolerant
  • Isothermal
  • Self-Regulating
  • Demonstration planned
    for 2024
  • Design Philosophy
  • Proven heat pipe technology developed by the Los Alamos National Laboratory for space
    application.
  • Does not use a bulk primary coolant
  • heat is removed from its core using passive heat pipes, limiting the number of its moving parts and
    providing overall plant simplicity.
  • The design utilizes the inherent safety features to enhance safety and self-regulation
    capability in the
  • fuel, moderator and
  • heat pipes technology