02/16/2012 - Updated mPower Presentation Slides, 'Core and Fuel … · 2012-07-19 · vl.26.03 *...

generation

B&W mPower Core and Fuel DesignUpdate Meeting (Redacted)

February 16, 2012© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. This presentation is the property of Babcock & Wilcox Nuclear Energy, Inc. Any copying, use, ordisclosure of this information without the written permission of Babcock & Wilcox Nuclear Energy, Inc. is strictly prohibited. This material is protected under tradesecret and unfair competition laws and the expression of the information contained therein is protected under federal copyright laws.

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mPower

Meeting Topics

* Introduction• Overview of Fuel Design Changes

* Mechanical Design Technical Report Feedback

* Core Thermal Hydraulics Update

* Core Design Update

* Benchmarking Status and Plans

* Core Startup and Operation Overview

* Conclusion

2

© 2012 Babcock & W~ilcox Nuclear Energy, Inc. All rights reserved.

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n7Power

B&W mPower Core Thermal HydraulicsUpdate

3

© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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1nPower

Core Thermal-Hydraulic Subchannel Analysis

~ VIPRE-01 mod 2.4f95 is used to model the core thermal-hydraulics

] [CCI per Affidavit 4(a)-(d)]

4© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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SPower

Cycle Plot - MDNBR

[

I[CCI per Affidavit 4(a)-(d)]


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minPower

DNBR Distribution[


6


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17Power

Cycle Plot - Peak Centerline Fuel Temperature[


© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. 7

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m743ower

Axial Plot- Centerline Fuel Temperature

[

I8© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [CC1 per Affidavit 4(a)-(d)]

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mPtower

Fuel Temperature Distribution[


9


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17Power

Critical Heat Flux Testing Status

STesting is being conducted at Stern Laboratories inHamilton, Ontario, Canada

> Two test series have been completed[


in 2012Three additional tests are planned(Tentative plan)[

I

[CMc per Affidavit 4(a)-(d)]© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. 10

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mPower

CHF Test Bundle

[

Unit cell testbundle beforeinsertion intothe flow channel



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1Power

Example of Test Results

[

][CCI per Affidavit 4(a)-(d)]

12


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1Power

Critical Heat Flux Correlation Development

[


© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.13

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m7Power

B&W mPower LatticeNeutronic Design


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2Power

Outline

* Methodology and Computer Codes

* Assembly Lattice Layout

" Lattice Neutronic Design Parameters

" Lattice Analysis Results

" Conclusions


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mPower

Methodology and CodesCode Code information

INTERPIN-4 Pin temperature calculation

Version Number: * Provides data for average fuel pin temperatures as a function of burnup and linear heat generation rate for

v4.01 the Studsvik CMS codes CASMO-5 and SIMULATE-3

e INTERPIN-4 output feeds directly into CASMO-5 and SIMULATE-3 inputs

CASMO-5 Lattice layout and characterization

Version Number: * Two dimensional lattice physics (transport) code using the ENDF/B-VII.0 based 586 group cross section library

V2.00.00 * Neutron energies cover the range from 0 to 20 MeV

CIMS-LIN K Cross-section processing

Version Number: 9 Processes CASMO-5 Card Image files into a binary formatted nuclear data library for use by SIMULATE-3

vl.26.03 * Includes 2-group macroscopic x-sections, discontinuity factors, fission product data, detector data, pin power

reconstruction, kinetics, isotopics, etc.

SIMULATE-3 Reactor core loading and cycle projection simulation

Version Number: * Advanced three-dimensional, two-group nodal code for reactor core simulation and analysis

v6.09.23 * The code is based on a neutronics model which employs fourth-order polynomial representations of the

intranodal flux distributions in both the fast and thermal groups

* One of the key features of SIMULATE-3 is the pin power reconstruction capability


generation

miwrwerAssembly Lattice Layout

Fuel assembly conceptually similar to [a conventional 17xl 7 square latticePWR, with the exception that isshorter

[


I[CCI per Affidavit 4(a)-(d)] 17


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Assembly Layout SummaryFuel Assem bly

Lattice array 17x17

[

]© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [CCI per Affidavit 4(a)-(d)] 18

[

generationm•wer

Lattice Layout Example



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mPowerLattice Neutronic Design Parameters

[

]

[CCl per Affidavit 4(a)-(d)] 20


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LattroDerLattice Neutronic Design Parameters

[

]

[CCI per Affidavit 4(a)-(d)]


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LtowerLattice Nomenclature

[



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[

] 23

@ 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [CC1 per Affidavit 4(a)-(d)]

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mPower

[

24

@ 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [CCI per Affidavit 4(a)-(d)]

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m2we5[

© 02Bbok&Wlo NcerEegIc llrgt eevd - C I e fia i ()() ] 25

@ 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [CCI per Affidavit 4(a)-(d)]

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mPower

Conclusions* The B&W mPower lattice is based on the industry

standard 1 7x1 7 fuel assembly° CASMO-5 has been used to create and analyze

lattice cross sections for the construction of fuelassemblies in SIMULATE-3 for the mPower coreloading and cycle management design

* Lattice burns provide a window into the behavior ofassemblies constructed from the various CASMO-5cross section sets


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niPower

B&W mPower Core Loading andManagement


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mPower

Outline

* Core Design Parameters

" Core Loading

" Control Rod Patterns and Cycle Management

* SIMULATE-3 Summary Results

" Conclusions


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mPowerCore Design parameters

Core Data

Total number of assemblies L --

Estimated core loading

Rated thermal power level

Rated thermal power density

Rated core flow

Bypass flow

Reference dome pressure

Reference reactor mid-plane pressure

Reference inlet temperature

Reference outlet temperature

Subcooling (outlet) ] [CCI per Affidavit 4(a)-(d)]



generationmJ ower

Core Design ParametersEnergy Parameters

Cycle length 48 months

Cycle capacity factor

Cycle energy (estimated)

EOC Power Level

Cycle hot target k-effective

Cycle cold target k-effective ] [CCI per Affidavit 4(a)-(d)]

Margin Parameters

Minimum cold shutdown margin [

Maximum nodal peaking ] [CCI per Affidavit 4(a)-(d)]

Control Parameters

Exposure between sequence exchanges [

Control rod utilization

Parked control rod positions preferred ] [CCI per Affidavit 4(a)-(d)]


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1POwerSimulate-3 Fuel Assembly

and Control Rod Assembly DefinitionFuel Assemblies

[


Control Rod Assemblies

[



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Core Loading - Fuel Assembly Types[

32

@ 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [M per Affidavit 4(a)-(d)]

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mPbwerCore Loading -Assembly Map

[



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mPowrer

Control Rod Sequence Definition[

][CCM per Affidavit 4(a)-(d)]


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lMowemCycle Management

[

]@ 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [CC1 per Affidavit 4(a)-(d)] 35

[

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Cycle Management (cont.)

© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [CCI per Affidavit 4(a)-(d)] ]36

[

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miPowerCycle Management (cont.)

I



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mPowerNodal Peaking[

]

[CCI per Affidavit 4(a)-(d)]38


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mPomerCore Axial Offset

[



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1Power[ Cold Shutdown Margin

]

[CCI per Affidavit 4(a)-(d)] 40© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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miPonwerHot Excess Reactivity

[



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mPowerControl Rod Movement[

]



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mPowerEOFP Axial Power and Exposure Profile

[

43 ]

© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.[CCI per Affidavit 4(a)-(d)]

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mPowerEOC RadialExposure

Distribution

]

[CCI per Affidavit 4(a)-(d)] 4© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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mPowerCore Design Results

[



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mPower

Conclusions

* SIMULATE-3 supports the design and analysis ofthe steady state operation of the B&W mPowerReactor reference design.

[


* Optimization studies are continuing.


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mzPowr

MCNPX BenchmarkLattice Physics Analyses


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mvPower

Outline

" Introduction" Lattice Studies* Reflector Analyses

" Conclusions


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Lattice Studies - MCNPX vs. CASMO-5

[



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mPowerLattice Benchmark Cold BOG ko, Results

[



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1PowerLattice Benchmark Hot BOG k., Results

[


51) 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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mPower

MCNPX Radial Reflector Benchmark Results

[



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m•IP0 rRadial Reflector Thermal Flux Profile

[

I

[CCi per Affidavit 4(a)-(d)]


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TPower

Radial Reflector Total Flux Profile[



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"mPwerRadial Reflector Thermal Current Profile

[

I[CMI per Affidavit 4(a)-(d)]


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1Power

MCNPX Lattice Physics Benchmark Conclusions

[

I[CMI per Affidavit 4(a)-(d)]


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mnPower

MCNPX Model of the B&W mPower ReactorReference Core Design


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mPower[

t I

]



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[



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m1Power

Core Model Description

[


60


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Cross Section of mPower Reactor Model at Core Mid-Plane[

I© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [CC1 per Affidavit 4(a)-(d)] 61

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m•PwerCore Model Description: Former, Basket, Vessel Wall, Air

[



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mPower[



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[



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m1Power

[



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mPower

Reactor Core Startup and Operation


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7mower

Presentation Topicsi Approach To Critical

• Reactor Heatup

* Power Ascension

* Cycle Operation


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mPower

Contents" Approach To Critical - Strategy

" Approach To Critical - Neutron Flux Monitoring

" Approach To Critical - Startup Neutron Sources

" Approach To Critical - CRA Sequences

" Approach To Critical - Simulated Approach To Critical


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m1PowerApproach To Critical - Strategy

I


69


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mPowerContents

* Approach To Critical - Strategy

* Approach To Critical - Neutron Flux Monitoring

- Startup Neutron Sources9 Approach To Critical

* Approach To Critical - CRA Sequences

- Simulated Approach9 Approach To Critical ToCritical


generationm wer

Approach To Critical - Neutron Flux Monitoring[

[CCI per Affidavit 4(a)-(d)] 71( 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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mPowerApproach To Critical - Neutron Flux Monitoring

[



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mPower

Contents

e Approach To Critical - Strategy

l Approach

* Approach

* Approach

* Approach

To Critical

To Critical

To Critical

To Critical

- Neutron Flux Monitoring

- Startup Neutron Sources

- CRA Sequences

- Simulated Approach To Critical

73@ 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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m owerApproach To Critical - Startup Neutron Sources

I



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mPowerApproach To Critical - Startup Neutron Sources

[

I[CM per Affidavit 4(a)-(d)] 75


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mPOwerApproach To Critical - Startup Neutron Sources

[

I[CCI per Affidavit 4(a)-(d)] 76


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mPower

Approach To Critical - Startup Neutron Sources[



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mAower

Contents* Approach To Critical - Strategy

* Approach To Critical - Neutron Flux Monitoring

* Approach To Critical- Startup Neutron Sources

* Approach To Critical - CRA Sequences

* Approach To Critical - Simulated Approach To Critical


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mPower

Approach To Critical - CRA Sequences[

] 79© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [M per Aff idavit 4(a)-(d)]

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POwer

Contentsi Approach To Critical - Strategy

* Approach To Critical- Neutron Flux Monitoring

* Approach To Critical- Startup Neutron Sources

" Approach To Critical - CRA Sequences

" Approach To Critical - Simulated Approach To Critical


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mnPowerApproach To Critical - Simulated Approach To Critical

[

][CCl per Affidavit 4(a)-(d)] 81


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inPowerApproach To Critical - Simulated Approach To Critical

[



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7Power

Approach To Critical - Simulated Approach To Critical[



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mPOwerApproach To Critical - Simulated Approach To Critical

[

][MCC per Affidavit 4(a)-(d)]


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mPower




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mPower


]



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mnowerApproach To Critical - Simulated Approach To Critical

[



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mPwer

Approach To Critical - Simulated Approach To Critical



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mulawerApproach To Critical - Simulated Approach To Critical

[



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mPkowerApproach To Critical - Simulated Approach To Critical

[

][CCl per Affidavit 4(a)-(d)]


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a TwerApproach To Critical - Simulated Approach To Critical

[



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mnPwer


I[CCM per Affidavit 4(a)-(d)]


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m~jower

[Approach To Critical - Simulated Approach To Critical

[CMl per Affidavit 4(a)-(d)]I


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nP awer




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mPower


]

[CCI per Affidavit 4(a)-(d)]95© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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mPower

Approach To Critical - Simulated Approach To Critical

[

© 2012 Babcock & Wilcox Nuclear Energy. Inc. All rights reserved. r,--,-m _ ^•:.J..: A i-t•. 96 ]

tIC per AHluidvIL ,4tal-tuij

generation

m7owerPresentation Topics

* Approach To Critical

" Reactor Heatup

" Power Ascension

i Cycle Operation


generationm wer

Contents" Reactor Heatup - Strategy

* Reactor Heatup - Flux/Power Monitoring

" Reactor Heatup - Reactivity Insertion/Feedback

" Reactor Heatup - Simulated Reactor Heatup


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mPowerReactor Heatup - Strategy

[



generationmlower

Contents* Reactor Heatup - Strategy


* Reactor Heatup - Reactivity Insertion/Feedback

* Reactor Heatup - Simulated Reactor Heatup


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m7Power

Reactor Heatup - Power/Flux Monitoring[



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mPower

Reactor Heatup - PowerlFlux Monitoring

[



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mPOwerContents

" Reactor Heatup - Strategy

" Reactor Heatup - Flux/Power Monitoring

" Reactor Heatup - Reactivity Insertion/Feedback

D Reactor Heatup - Simulated Reactor Heatup


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nPower

Reactor Heatup - Reactivity Insertion/Feedback

[



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mPowerReactor Heatup - Reactivity Insertion/Feedback

I[CCI per Affidavit 4(a)-(d)]105


generationin wer

Reactor Heatup - Reactivity InsertionlFeedback

[CCI per Affidavit 4(a)-(d)]© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

106

generationmlower

Contents* Reactor Heatup - Strategy


* Reactor Heatup - Reactivity InsertionlFeedback

* Reactor Heatup - Simulated Reactor Heatup


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mPowerReactor Core Heatup - Simulated Reactor Heatup

[

]© 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. [M per Affidavit 4(a)-(d)] 108

generationm wer

Reactor Core Heatup - Simulated Reactor Heatup[

I

[CCM per Affidavit 4(a)-(d)]


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[

I[CCM per Affidavit 4(a)-(d)]


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mPower



111@ 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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]



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[

I

[CCM per Affidavit 4(a)-(d)]


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]


114( 2012 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

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mPwer


I



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mPower


I

[CMI per Affidavit 4(a)-(d)]


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Smower


]



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m ower




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miPower

Presentation Topics* Approach To Critical

" Reactor Heatup

" Power Ascension

" Cycle Operation


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mwer

Contents" Power Ascension - Strategy

" Power Ascension - In-Core Power/Flux Monitoring

" Power Ascension - Ex-Core Power/Flux Monitoring

" Power Ascension - Simulated Power Ascension


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mPowerPower Ascension - Strategy

[

]



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mPower

Contents" Power Ascension - Strategy

" Power Ascension - In-Core Power/Flux Monitoring

" Power Ascension - Ex-Core Power/Flux Monitoring

" Power Ascension - Simulated Power Ascension


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I oPowe r

Power Ascension - In-Core Flux/Power Monitoring[



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mPowerPower Ascension - In-Core Flux/Power Monitoring

In-Core Detector Axial Locations

[

]



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inPower

Contents* Power Ascension - Strategy

* Power Ascension - In-Core Power/Flux Monitoring

* Power Ascension - Ex-Core Power/Flux Monitoring

* Power Ascension - Simulated Power Ascension


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mn- PowerPower Ascension - Ex-Core Flux/Power Monitoring

[



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mPowerPower Ascension - Ex-Core Flux/Power Monitoring

[



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POwer

Contents* Power Ascension - Strategy

* Power Ascension - In-Core Power/Flux Monitoring

* Power Ascension - Ex-Core Power/Flux Monitoring

* Power Ascension - Simulated Power Ascension


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Power Ascension - Simulated Power Ascension

[



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133


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Power Ascension - Simulated Power Ascension[

I



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135


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[

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I


138


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Power Ascension - Simulated Power AscensionI


139


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ina werPower Ascension - Simulated Power Ascension

[

I


140


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mPowerPower Ascension - Simulated Power Ascension

[

I


142


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I]


143


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144


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1mPowerPower Ascension - Simulated Power Ascension

[

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mPowerPower Ascension - Simulated Power Ascension[



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m74owerPower Ascension - Simulated Power Ascension

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153


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[

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158

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mPower

Power Ascension - Strategy[



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m742owerPresentation Topics

i Approach To Critical

e Reactor Heatup

* Power Ascension

e Cycle Operation


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Contents

i Cycle Operation - Strategy

o Cycle Operation - Simulated Sequence Exchange


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mPowerCycle Operation - Strategy

[



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mtnowerContents

* Cycle Operation - Strategy

* Cycle Operation - Simulated Sequence Exchange

163


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mPowerCycle Operation - Simulated Sequence Exchange

I

I



[

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Cycle Operation - Simulated Sequence Exchange

][CMl per Affidavit 4(a)-(d)]


[

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mnPowerCycle Operation - Simulated Sequence Exchange



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Cycle Operation - Simulated Sequence Exchange[

I



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mPowerCycle Operation - Simulated Sequence Exchange

Core Outlet Temperature Variations During Sequence Exchange

[

]t)2012 Rahrock &. Wilcox Nuclear Enprmv. Inc. All riphts reserved. rCCi ner Affidavit 4lai-frfll 171

. . . . . .. . .. . .. .. . . ... .. . ... . 0 1 . ... . .. . 0 ... .. . . . . Lvv" Iv ............. I•l I•lJ

02/16/2012 - Updated mPower Presentation Slides, 'Core and Fuel … · 2012-07-19 · vl.26.03 *...

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Transcript of 02/16/2012 - Updated mPower Presentation Slides, 'Core and Fuel … · 2012-07-19 · vl.26.03 *...