SMR- 4 BWXR-300 Flashcards by Missy Balachorek

BWRX is a ___ cooled small modular reactor that is __ based

water
land

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BWRX-300 is the ____ and
most ____ BWR design

simplest
innovative

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Built by ______

General Electric-Hitachi

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____MW(e)
* ____-cooled
* _____ circulation SMR

300
water
natural

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Utilizing ____,_____
_____ driven safety systems.

____th generation of the Boiling
Water Reactor (BWR)

simple, natural phenomena

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what does bwr stand for

boiling water reactor

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The design has been developed
with a strict adherence to a
philosophy which follows the
_____ guidelines.

IAEA Defense-in-Depth

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slide 2 has depiction of reactor

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Main Design Features - Nuclear Steam Supply System

Utilizies the proven supply chain

 ___ and the _____driven safety features from the ____

ABWR
natural phenomena
ESBWR

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For its primary circuit, or nuclear boiler system.

Components include (LIST 1-5)

 the Reactor Pressure Vessel (RPV),

 fine motion control rod drives (FMCRDs), control blades, Chimney, separators, and dryer.

 The RPV and the chimney height are scaled optimally to the thermal output and natural circulation

 The nuclear boiler system delivers steam from the RPV to the turbine main steam system; and delivers feedwater from the
condensate and feedwater system to the RPV.

 It also provides overpressure protection of the reactor coolant pressure boundary (RCPB).

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Main Design Features - Reactor Core

The BWRX-300 reactor core comprises
____, ____, and
_____ instrumentation

fuel assemblies
control rods
nuclear

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Main Design Features - Reactor Core

It has ___ fuel bundles

The core ____configuration has _____
on the ___ and ____sides which provides ____

The fuel bundles are arranged in a _____
configuration located _____

The ___flows ____ through the _____

240
lattice
equal spacing
control rod
non-control rod
increased shutdown
near cylindrical
inside a core shroud
coolant
upward
core

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Main Design Features - Reactivity Control Reactivity

control is provided by ___

control rods

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Main Design Features - Reactivity Control Reactivity

__ or ___ neutron absorbers and ____ neutron absorber loaded in the ____

 The control rods are moved using the____

B4C or Hf
burnable
fuel rods
FMCRDs

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Main Design Features - Reactivity Control Reactivity

FMCRD’s - ____ of moving ____

_____ fine control for reactivity control during ____ and _____during a ____

GE Hitachi claims they are ____
No ____, ____and ____

2 means
control rods

motor driven
normal operation
hydraulic rapid insertion
scram

independent
separation,
diversity and
redundancy

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Main Design Features –
Reactor Pressure Vessel and Internals

The RPV assembly consists of a____ with ____, _____ and ______

pressure vessel.
removable head
internal components
auxiliaries

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The major reactor internal components

 the core and core plate,
 top guide, control rod guide tube, control rod drive
housings, and orificed fuel supports,
 chimney,
 steam separator, and steam dryer assembly

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Main Design Features – the reactor coolant system (RCS)

___ is _____ driven and provides cooling of the ____—- in all ___ and all ____conditions.
_____ utilization of ______modelling and operational information
The relatively tall RPV
____driving forces to produce_____

cooling
natural circulation
reactor core
operational states
postulated off normal

Supply chain
Natural circulation

RPV
circulation
abundant core coolant flow.

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Safety Features –
Engineered Safety System Approach and Configuration

__ passive cooling systems

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passive cooling systems

isolation condenser system (ICS)
passive containment cooling system (PCCS)

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isolation condenser system (ICS) removes

decay heat

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passive containment cooling system (PCCS) removes and maintains

removes decay heat
maintains containment within the pressure limits for design basis accidents

Safety Features – Safety Design Philosophy

The defence-in-depth (D-in-D) concept uses _____ to define the interface between the ___and the ____ (later).

Fundamental Safety Functions (FSF)
defence lines
physical barriers

Safety Features - Decay Heat Removal SystemIsolation Condenser System

The ICS removes decay heat after any reactor isolation during
power operations and provides overpressure protection Sudden
reactor isolation at various operating conditions
For example, Loss of Coolant Accidents (LOCAs)
* ICS is initiated automatically on RPV overpressure or LOCAs
* The ICS consists of three independent loops, each containing a
heat exchanger, with capacity of 33 MW(t).
* The ICS tubes condense steam from the RPV on the inside surface
and transfer heat on the outside surface to the IC pool which is
vented to the atmosphere.
* This steam condensation and gravity allow the reactor to cool
itself for a minimum of 7 days without power or operator action.

Safety Features - Decay Heat Removal SystemIsolation Condenser System The ICS removes _____ after any _____ during _____ and provides _____Sudden____ at various operating conditions For example, ____

decay heat reactor isolation power operations overpressure protection reactor isolation Loss of Coolant Accidents (LOCAs)

Safety Features - Decay Heat Removal SystemIsolation Condenser System * ICS is initiated _____on _____or ____

automatically RPV overpressure LOCA's

Safety Features - Decay Heat Removal SystemIsolation Condenser System * The ICS consists of ____ ______loops, each containing a _____, with capacity of __ MW(t).

3 independent heat exchanger 33

Safety Features - Decay Heat Removal SystemIsolation Condenser System * The ICS tubes c____ from the ___ on the ____ and transfer ___ on the_____to the ____which is ___ to the _____

ondense steam RPV inside surface heat outside surface IC pool vented atmosphere.

Safety Features - Decay Heat Removal SystemIsolation Condenser System this ______ and _____ allow the reactor to cool itself for a minimum of __days without ___.

steam condensation gravity 7 power or operator action

Safety Features - Containment System * The containment surrounds the ____

RPV, FMCRD's piping systems isolation valves

Safety Features - Containment System utilizing the ____, the containment design ____ and___ of the containment are within values used in the operating __,__ and __.

supply chain design pressure temperature BWR fleet, the ABWR and ESBWR.

Safety Features - Containment System * The ___ valves ____to the ___during a ______ it is Designed to ____ ___utilized in almost all previous BWRs is not needed.

RPV isolation limit the steam released containment postulated large break LOCAs eliminate LOCAs Suppression pool

Safety Features - Containment System * Postulated ___ -> ___,_ and ___can handle for a minimum of __ hours without __ or __

small break LOCAs ICS, PCCS dry containment 72 ac power operator action

Balance of Plant -Electrical Systems * The electrical system is a ___ power supply and _____for the power plant.

completely integrated transmission system

Balance of Plant -Electrical Systems * It is divided into subsystems based on _____.  Each subsystem has appropriate levels of ___ and ___quality for the systems it powers  Each subsystem provides ____to various __  ____n path for the __ to the ___

safety classification. hardware and software reliable power plant electrical loads Transmission main generator utility switchyard/grid.

Balance of Plant – Instrumentation and Control Systems * The I&C system (also referred to as the _____ or “___) is a ______and____for the ____. * The I&C comprises of ___ main platforms.  Each platform has appropriate levels of ___ and ___quality (corresponding to the systems they control), and provides ___,___,___ and___

distributive control and information system DCIS completely integrated control monitoring system power plant 3 hardware software control monitoring alarming recording functions

Balance of Plant - Fuel Cycle Approach * The design has the same ____as operating BWRs ___ through lifetime

open fuel cycle once

Balance of Plant - Fuel Cycle Approach * During every ____outage, __% to ___% of the ___ in the core are ____ ____ stays in the core for ___ until it is discharged. __ to __cycles

refuelling 15 25 bundles replaces fresh fuel fresh fuel several cycles 4 7

Balance of Plant - Fuel Cycle Approach * When removed from the core, used fuel is _____ for __to ___ years  transferred to ____ that can be removed from the ____ and stored ___

stored in the fuel pool inside the reactor building 6 8 storage casks reactor building outside

Plant Layout Arrangement The balance of plant includes:

 the turbine building, radiation waste building, control building and yard.  The turbine receives high-quality dry steam directly from the RPV,  the condenser system cooled by the ultimate heat sink and the feedwater system that returns the coolant into the reactor.

Plant Layout Arrangement * It also consists of process systems - - - - -

 plant service water system (PSWS),  the component cooling water system (CCW),  the makeup water system (MWS),  the condensate storage and transfer system (CSTS), and  the chilled water system (CWS).

Plant Layout Arrangement * The reactor building extends ____where the _____ and ____ mostly reside. * The Reactor Building contains _____ in the plant. * The ___floor is ____ grade level. * The underground construction of the reactor building utilizes proven techniques in the mining and shaft sinking industries to___ the use of ___ and ___

below grade primary containment and RPV all of the safety related components refueling above minimize concrete and engineered backfill.

gen___ type :___

3 water cooled

___ cycle with no secondary ___ and ______

direct steam generator pressurizer

___enriched (___% U-235) oxide fuel in__ cladding

low 3-5 metal

____serves as moderator

water

coolant circulated through core with ___ circulation

natural

Pressurized water reactors (PWR's) typical __cycle steam plant with ___generators and __ for steam generation ___ enriched ___% U-235 ____ serves as moderator coolant circulated through ____

dual steam pressurizer low 3-5 water coolant forced circulation

isolation condenser system - impact on safety ___ trains provide __removal/_ control mild transient response due to __ steam volume in RPV no need for ____ ___ isolation condenser train required to respond to transient __day coping time for station blackout

3 heat pressure large safety relief valves 1 7

fine motion control rod drive (FMCRD) inserted in _____ and penetrates bottom head of ___ control rod is__ to top of FMCRD __ driven, __drive positioning system

CRD housing RPV COUPLED motor screw

major functions of steam cycle direct __ from reactor to ___ and __steam loads use steam energy to generate ___ for in-house and off-site

dry steam main turb auxiliary

major functions of steam cycle ___ steam after steam performed its function ___ condensed water prior to returning to reactore

condense clean

HCU stands for ___ provides __ pressure water to rapidly insert __ during scram __HCU provide hydraulic force for __ control rods __total HCUs for __control rods

hydraulic core unit high control rods 1 2 29 57

control rod drive primary functions ____from normal operation or accident conditions control ___, ___power and ___flux distribution

shut down reactivity reactor neutron flux