SMR-5 - SFR Flashcards
1
Q
gen ___ reactor
A
4
2
Q
scfr stand for
A
sodium cooled fast reactor
3
Q
arc has ___ yr refueling cycle
terra has ___ month refeuling cycle
hight temp gas reactors - _____
molten salt reactps______
A
20
18/20
do not work yet
material issues
4
Q
mircor smr
,,_ mega watts
A
5
10
20
5
Q
grid scale smrs
A
gen 3+
gen 4 (advanced reactor)
6
Q
gen 3+ types
A
water cooled
7
Q
gen 4 types
A
sodium cooled fast reactor
high temp gas reactor
molten salt
8
Q
why sodium?
A
6th most abundant element
can move a lot of heat ( high thermal conductivity -> 85 x that of water)
heat capacity bad = does not absorb heat
9
Q
sodium is Liquid between___ at atmospheric pressure.
A
98℃~881℃
10
Q
Why is water a bad choice
A
its a good solvent
it eats reactor @ high pressure and also requires high pressure
results in lined thick walls that are heavy duty to contain
11
Q
why is sodium better than water
A
does not need to boil or a pressure vessel to contain
since it operate just above atmospheric at hight temp
id there is a leak - there is no driving force to pour out
12
Q
Sodium Fast Reactor 101
* The SFR uses ____ as the reactor
coolant, allowing operation at ___, ____ force for _____.
A
liquid sodium
low pressure
reducing driving
off-site dose
13
Q
Sodium Fast Reactor 101
Much of the basic technology for the SFR
has been established in former fast reactor
programs, so this is not a _____Technology.
- High level of safety achieved through
___ and ___ means with significant safety margins. - SFR’s with ___ are ideal for _____ and _____ applications that create broad market
opportunities.
A
FOAK
inherent
passive
superheated steam
electrical grid
industrial heat
14
Q
ARC-SFR’s Evolutionary Path
same type of evolution as ____ did in canada with incremental increases in capacity
A
CANDU
15
Q
ARC-100 Integration with Industry & Energy Systems
industrial applications
A
industry
hydrogen production
new chemical processes
clean water
medical isotopes
16
Q
proven inherent _______ safety
A
walk away
17
Q
ARC-100 Integration with Industry & Energy Systems
electrical gen
A
electrical grid
heat storage for peaking ability
renewables - wind and solar power
18
Q
reactor building is ___m (includes____)
outside is _____
A
18
all safety grade
high grade industiral
19
Q
overall site area ___m^2
main building ___m^2
all buildings included ____
A
54000
5400
10075
20
Q
ARC-100 entire steam and electricity production is ___, so easily adaptable to different configurations to support
from 100% electricity to 100% heat or anywhere in-between
A
industrial Standards
21
Q
ARC-100 Design ____of Safety-Related Systems
A
Reduces Footprint
22
Q
how it works
__ sodium loops
sodium circulates at __psi
steam generator take __psi
A
2
60
2200
23
Q
reactor vessel system
design is based on the established ____
(SFR) technology, where a____
- The Reactor Vessel is enclosed within the ___, which serves as a ___.
- The Reactor Vessel is filled with ____and has an ___ kept s____. All access to
the fuel and various components within the Reactor Vessel is achieved from the __, eliminating penetrations of the
___ of the reactor vessel below ___
A
pool-type Sodium-Cooled Fast Reactor
pool of sodium is contained within the Reactor Vessel and top plate.
Guard Vessel
leak jacket
sodium
argon cover gas blanket
lightly above atmospheric pressure
the top of the reactor
pressure retaining sections
the top plate
24
Q
TRC stand for
A
Technology ready level
25
everything in vessel is ___
extractable
26
___ core
__ transfer machine
circular
in vessel
27
core rods need to be replaced ___ years
6-7
28
fuel is good for __ yrs
20
29
_ control rods
_ safety control rods
6
3
30
ave enrichment __
candu enrichment__
13.1
0.4-0.7
31
Reactor Core and Fuel Assemblies
The U-10%Zr (Uranium with 10 wt %
Zirconium) sodium-bonded binary metallic
fuel has a____ temperature that provides a ___margin to fuel ______ during ___scenarios.
low operating centerline
large safety
centerline melting
postulated accident
32
Reactor Core and Fuel Assemblies
__ fuel in __ cladding is surrounded by ___
__ pool and not ___ pool
addition of ___ helps to stabilize the __
metal
metal
sodium
cold
hot
zirconium
uranium
33
Primary Heat Transport System (PHTS)
is the ___ loop of the ___ which is contained within the ___.
coolant
reactor core
Reactor Vessel
34
Primary Heat Transport System (PHTS)
* Since Sodium is a ____ and magnetic, __ submersible ___provide ___within the ___
liquid metal
4
Electro-Magnetic (EM) pumps
sodium circulation
reactor vessel
35
Primary Heat Transport System (PHTS)
* The___sodium is pulled out of the ____ at the ____through the ___ and into the cold pool.
hot
primary sodium pool
outlet of the core
Intermediate Heat Exchangers (IHXs)
cold pool
36
Primary Heat Transport System (PHTS)
* The ____bridge the ____and provide the means for ____ to the ____
Intermediate Heat Exchangers (IHXs)
hot and cold pools
transferring heat
Intermediate Heat Transport System (IHTS).
37
Intermediate Heat Transport System
is the ___ system for transporting __from
the __ to the ___
sodium fluid
reactor heat
IHXs
Steam Generator.
38
Intermediate Heat Transport System
consists of __ piping loops between the ___
which reside in the ___, and the Steam Generator.
Intermediate Heat Exchangers (IHXs),
Reactor Vessel
steam generator
39
Intermediate Heat Transport System
* Each piping loop includes an __ and
___ in the___. The system also includes instrumentation for __and a __ for ___protection for the __, __and ___
EM pump
permanent magnet flowmeters
cold leg.
detecting
Steam Generator tube leaks
rupture disc driven pressure relief line
overpressure
Steam Generator Shell
intermediate piping
intermediate Heat Exchangers (IHXs).
40
Intermediate Heat Transport system
the __, the __ and the ___are located in the ____
Steam Generator
sodium dump valve
intermediate Sodium Processing System (ISPS)
Steam Generator & Auxiliaries Enclosure.
41
only sodium outside the reactor building is ___
hot and cold piping
42
nuclear steam supply system
slide 23
43
Simplified Turbine/Generator Island
The ARC-100 produces ____ and is small enough to take advantage of a ____ and an ____ as well a standard model currently well proven and deployed for GasTurbine with Steam Recovery applications.
superheated steam
single casing steam turbine
aircooled generator
44
* Simplified Turbine/Generator Island
No ___, ___ or ___ typical for water cooled
Reactors.
reheater
moisture separator
multiple
casing (HP+3LP)
45
* Simplified Turbine/Generator Island
* Due to ___ of the ARC-100, the
Balance of Plant is not required as a ___, ___procurement costs.
passive safety
safety related heat sink
reducing
46
TRL Assessment Observations
All System, Structure & Component (SSC) TRL Levels at ____
*
Several SSC Options for Operational and Maintenance Optimization in____
* No SSC’s in ___.
Demonstration &Deployment readiness states
Development Stage.
Research Stage
47
Safety Characteristics Emergency core cooling
The ARC-100 is equipped with ___ emergency core cooling systems that act to remove heat from the ___
two independent
reactor core, RVACS and DRACS.
48
2 Emergency core cooling systems and how many
Reactor Vessel Auxiliary Cooling System
(RVACS) - has 4 only required 1
Direct Reactor Auxiliary Cooling System
(DRACS) - has 3 only require 1
49
Large Operating Safety Margins & Natural Circulation
* ___primary system
* Coolant operates at ___C , boils at >__ C
* No stored ___, eliminates ___ driving force
* No potential for ___generation
* Elimination of__
* Metallic alloy fuel,____ cladding
Ambient pressure
355-510º
900º
mechanical energy
LOCA
in-core H2
Zr/UO2/H2O
Metallic alloy
Steel
50
Large Operating Safety Margins & Natural Circulation
* ___ temperature ___in metallic fuel
* Thermal conductivity ___ ___ than oxide fuel
* ___stored energy in the fuel
___circulation – long term cooling without need for active components
* DRACS – ____operating
* Fully _____RVACs
* No long term need for __systems
small
temp
10x better
Reduced
* Natural
need for active components
continually
independent
offsite or emergency AC power
51
The Unprotected Station Blackout Does Not Damage the Plant
___ temperatures peak within ___ minute
* Decrease below __as ___
* ___ fuel melting and sodium boiling margins maintained
* __temperatures rise ____ threshold
* __pool temperature peaks at __C below
____ limit of ___C
In-core
first
pre-transient temperatures
power decreases
Large
Clad
barely above slow
eutectic
Hot
542°C
Service Level D
704°C
52
Unprotected Station Blackout
* Loss of power to ___pumps
* Failure of RPS to ___
* Large negative reactivity from ___feedbacks counters increasing ___
all
scram the
control rods
radial expansion and axial
expansion
power-to-flow ratio
53
Beyond Design Basis Accidents
Severe accidents, those that would lead to fuel damage, are precluded in the ARC-100 by virtue of the____ response of the reactor.
self-protecting
54
* Anticipated Transients Without Scram (ATWS) do not lead to_____ as demonstrated by actual tests in the EBR-II.
* Regardless, tests have been undertaken in the TREAT facility by created a cladding breach with a burst of _ times power that also demonstrated ___reactivity.
* In the event of Beyond Design Basis Accident
- Fuel retains the ___
* Sodium scrubs a significant amount of those which __
fuel
damage
4
strong negative
majority of fission products
might be released from
fue
55
The selection of __, in combination with ___, results in Inherently Safe Characteristics
metallic fuel
sodium coolant
56
Sodium Fire
__ burn rate, __calorific value, __flame
* ___fire extinguishing agent
Slow
low
weak
Dry Powder
57
__ fires are __ likely to spread/expand than oil fires
sodium
less
58
Sodium Fire
The ARC-100 reactor has design features enabling the early detection of ___
* Sodium containing systems, as well as the ___, are provided with an __ to preclude the ingress of air. Such ingress of air can result in reaction with __. Similarly leaks of sodium directly into spaces that are ___can result in fires.
sodium leaks
NaK containing Direct Reactor Auxiliary Cooling System (DRACS – utilized for decay heat removal)
inert gas cover
sodium and fires
not inerted
59
The benefits of Sodium as a coolant for heat transfer, ___, __ and __ far outweigh the
known industrial risk, which is minimized with modern design practices.
lack of corrosion
scrubbing
effect on fission products
non-pressurized operation
60
Sodium Fires
* The ARC-100 design is equipped with not only features that protect against leaks of __and ___ but also features that will arrest __ where they to occur and facilitate the __ should they occur.
air into the sodium space
leaks of air into the sodium space
fires
fighting of such fires
61
Sodium Water Reaction (SWR)
design mitigation summary
material selection
water dump tank included in configuration to allow for rapid blowdown of steam/water within SG (steam generator) upon detection of sodium water reactor
pressure relief valves in steam and feedwater lines
capability to isolate steam and feedwater lines
interface support from ihts sodium water reactors protection line
worst case - multiple disk burst and limits the pressure pulse back to intermediate ihx
62
Sodium Corrosion
The corrosion of structural materials in liquid sodium is strongly affected by the presence of ___.
To maximize the lifetime of structural materials (mainly stainless steels) in SFRs, ____of the sodium is necessary to____
oxidizing (oxygen) and carburizing (carbon) impurities
purification
control the oxygen level.
63
sodium corrosion
Comprehensive studies have been performed, and reliable industrial experience has been gained showing that corrosion rates in sodium are significantly ___than those in ___coolant systems.
Corrosion of immersed stainless steel in sodium is ___if sodium ___ is maintained.
lower
water-based
not a concern
purity
64
No significant corrosion of materials in the sodium circuits of the BN-10 reactor occurred during ___years of operation.
In EBR-II after the sodium was drained from the primary tank the condition of the tank and the components submerged in sodium was ___
There was absolutely no corrosion of the stainless steel after ___ years in contact with hot sodium.
44
pristine.
35
65
Demonstrated a SFR with metal fuel
can be ___ over a ____ range.
passively controlled
large power
66
* simulated
Dynamic simulation of the reactor, secondary circulation and steam generator. The reactor was able to load follow at _% of
rated power per minute between ___% and __%.
* Fast reactors are not affected by ___ poisoning versus WRs
6
100
40
xenon
67
licensing Status of the ARC-100
completed :
in progress:
Phase 1: Pre-Licensing
Assessment of Compliance
with Regulatory
Requirements
Phase 2: Pre-Licensing
Assessment for Any Potential
Fundamental Barriers to
Licensing
68
– Licensing Status of the ARC-100 CNSC VDR Phase 2 Update
* Focus Areas submissions were placed into __groupings.
* ARC has submitted all packages for the __Focus Areas to the CNSC.
* ___RFI’s answered.
* Target Draft Composite Report from CNSC __ 2025.
4
19
all
March
69
Resource Utilization and
Waste
Currently, an ___is the planned approach.
* After a ___-year cycle is complete the used fuel will be stored ____ to allow ___ decay.
* At a suitable time the used fuel will be ___storage.
* Should fuel reprocessing become acceptable in Canada, the ARC-100 can operate with ___due to the ___
* The ARC-100 can use __from existing used fuel stockpiles, thus extending the uranium
resource (___uranium mining, __, ___ requirements)
open cycle
20
within the facility
thermal cooling and radioactive
extracted and transferred to on-site dry
reprocessed fuel
fast neutron spectrum.
fissile materials
decreases
conversion
enrichment
70
waste
Interim Storage (1) – In-Vessel Storage
* ARC-100 Reactor Vessel (RV) 3D model to include spent fuel storage with the capability of storing +___used fuel assemblies until spent fuel is suitable for transfer to dry storage.
99
71
* In reactor design, it is advantageous for
security, non-proliferation, and cost for spent fuel to be stored within the ___instead of needing a separate spent fuel pool.
* Efforts were made in 3D modeling software to allow the RV to store ___ fuel assemblies.
* There will be __rows of spent fuel storage
within the shielding surrounding the core and that the __ be level with the ___
* This prevents any ___ with the __
RV
108
two
spent fuel
core fuel.
geometrical interference
Upper Internal Structure (UIS)
72
Interim Storage (2) – Commercially Available Dry Storage
* The system features a _____for UNF
assemblies.
* The DSCs will be stored inside a ___ that is a robust, fortress-like__ storage overpack.
dry shielded canister (DSC)
horizontal storage module
(HSM)
concrete
73
Long Term Storage – Nuclear Waste Management Organization
and the Deep Geological Repository
NWMO in charge
74
The Potential for a Long-Term Fuel Cycle
The ARC-100 fuel after __ years of operation
contains as much fissile content (Pu, U235) as at the ___(U235 only)
* The __ process could be used to
recover the ___ elements for recycling
into fresh fuel.
* ___ feed eliminates need for ___
___ fuel also a potential feed for __
20
Beginning of Life (BOL)
pyroprocessing
Transuranic
Metal fuel
oxide
reduction.
* LWR oxide
pyroprocessing
75
self shut down explained
enrichment levels create fission
metal expands when heated
entire reactor expands when heated
kills reactivity and shuts itsself down
passive shutdown
no more reactivity for chain to continue
chain reaction (atoms further apart - when it cools down)
it gives it time and it oscillates up and down
never gets above boiling temp of sodium
proven walk away safety
76
also know as
fast neutron spectrum small modular reactor
77
* ___-cooled, ____flux,____ -type reactor with ___fuel
Sodium
fast
pool
metallic
78
ARC-100 addresses the ___ challenges which limits public acceptance/expansion of nuclear. they are :
4
size
can be fueled with recycelable fuel
uses metalic alloy not oxide - walk away safe
reduces nuclear proliferation risk (replace entire cartridge after 20yrs)
