ML082530272: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 2: Line 2:
| number = ML082530272
| number = ML082530272
| issue date = 07/23/2008
| issue date = 07/23/2008
| title = Vermont Yankee July 2008 Evidentiary Hearing - Applicant Exhibit E4-02-VY, Horowitz Cv
| title = July 2008 Evidentiary Hearing - Applicant Exhibit E4-02-VY, Horowitz Cv
| author name = Horowitz J
| author name = Horowitz J
| author affiliation = - No Known Affiliation
| author affiliation = - No Known Affiliation
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:/-Ac-S H-S 112                                                                                 DOCKETED USNRC August 12, 2008 (11:00am)
{{#Wiki_filter:/-Ac-S H-S 112 DOCKETED USNRC August 12, 2008 (11:00am)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF RESUME Jeffrey S. Horowitz, ScD PROFESSIONAL EXPERIENCE 1985 - Present Independent consultant working in the nuclear and mechanical engineering fields. Consultant to EPRI (Electric Power Research Institute) on single and two-phase flow-accelerated corrosion (also known as erosion-corrosion), cavitation, thermal-hydraulic analyses, void fraction correlation and service water corrosion.
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF RESUME Jeffrey S. Horowitz, ScD PROFESSIONAL EXPERIENCE 1985 - Present Independent consultant working in the nuclear and mechanical engineering fields. Consultant to EPRI (Electric Power Research Institute) on single and two-phase flow-accelerated corrosion (also known as erosion-corrosion), cavitation, thermal-hydraulic analyses, void fraction correlation and service water corrosion.
Principal creator of CHEC, CHECMATE and CHECWORKS, the computer programs which predict single-phase and two-phase flow-accelerated corrosion. CHECWORKS is currently used to improve maintenance efficiency and enhance safety in more than 150 nuclear units worldwide.
Principal creator of CHEC, CHECMATE and CHECWORKS, the computer programs which predict single-phase and two-phase flow-accelerated corrosion. CHECWORKS is currently used to improve maintenance efficiency and enhance safety in more than 150 nuclear units worldwide.
Consultant to Arizona Public Service, the CANDU (Canadian Deuterium Uranium reactors) Owners Group, Exelon Corporation, Ontario Power Generation, Inc., Pacific Gas & Electric and Southern California Edison on issues of flow-accelerated corrosion and nuclear safety.
Consultant to Arizona Public Service, the CANDU (Canadian Deuterium Uranium reactors) Owners Group, Exelon Corporation, Ontario Power Generation, Inc., Pacific Gas & Electric and Southern California Edison on issues of flow-accelerated corrosion and nuclear safety.
Co-author of three books and 34 published EPRI reports. Sole author of 16 published EPRI reports.
Co-author of three books and 34 published EPRI reports. Sole author of 16 published EPRI reports.
1980-1984      Program Manager, U.S. Department of Energy, 9800 South Cass Avenue, Argonne, Illinois, 60439, 630-252-2000, Frank Herbaty, supervisor:
Program Manager, U.S. Department of Energy, 9800 South Cass Avenue, Argonne, Illinois, 60439, 630-252-2000, Frank Herbaty, supervisor:
Managed substantial portions of the Industrial Co-generation, Magneto-hydrodynamics (MHD) and Ocean Thermal Energy Conversion (OTEC)
Managed substantial portions of the Industrial Co-generation, Magneto-hydrodynamics (MHD) and Ocean Thermal Energy Conversion (OTEC)
Programs at the Chicago Operations Office. The annual value of the work I managed was about $10 million.
Programs at the Chicago Operations Office. The annual value of the work I managed was about $10 million.
Promoted from GS- 13 to GS- 14.
Promoted from GS-13 to GS-14.
1977 - 1980   Mechanical Engineer, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439, 630-252-2000. D..Norman Sather, supervisor:                                               IUULr.,-tl i~t3uLATfV IntheMatterof   5lLý¶> tjje Oocket No, .,L...-.p                       jV.~j~j, Official Exhibit No.--"i --, U'f OIFFERED t)FFERED by4       ý)by           Intervenor NRC Staff           Other W2Iwinessmpanol-K FJC g IDENTIFIED) oni3&3 Adton TakmW                     REJECTED W NIWN
1980-1984 1977 - 1980 Mechanical Engineer, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439, 630-252-2000. D..Norman Sather, supervisor:
IUULr.,-tl i~t3uLATfV IntheMatterof 5lLý¶> tjje jV.~j~j, i Oocket No,.,L...-.p Official Exhibit No.--"  
-- U'f OIFFERED by4  
ý)
t)FFERED by Intervenor NRC Staff Other IDENTIFIED) oni3&3 W2Iwinessmpanol-K FJC g Adton TakmW REJECTED W NIWN


Government Technical Manager on several, multi-million dollar OTEC power systems studies and heat exchanger construction programs.
1973-1977 Government Technical Manager on several, multi-million dollar OTEC power systems studies and heat exchanger construction programs.
Conducted design studies, computer modeling and laboratory testing on a metal-hydride heat pump system.
Conducted design studies, computer modeling and laboratory testing on a metal-hydride heat pump system.
Promoted from Assistant Mechanical Engineer to Mechanical Engineer.
Promoted from Assistant Mechanical Engineer to Mechanical Engineer.
1973-1977        Principal Engineer, Combustion Engineering, 1000 Prospect Hill Road, Windsor, CT 06095, 860-688-1911, Dr. Hector Guerrero, supervisor:
Principal Engineer, Combustion Engineering, 1000 Prospect Hill Road, Windsor, CT 06095, 860-688-1911, Dr. Hector Guerrero, supervisor:
Lead engineer on a series of nuclear safety experiments including tests on an alternate emergency core cooling system, steam generator depressurization, re-flood heat transfer and an innovative primary system flow meter.
Lead engineer on a series of nuclear safety experiments including tests on an alternate emergency core cooling system, steam generator depressurization, re-flood heat transfer and an innovative primary system flow meter.
1972-1973        Nuclear Engineer, Quadrex Corporation, 477 Division Street, Campbell, California, (company now defunct), Randolph Broman, supervisor:
Nuclear Engineer, Quadrex Corporation, 477 Division Street, Campbell, California, (company now defunct), Randolph Broman, supervisor:
Conducted various nuclear safety analyses.
Conducted various nuclear safety analyses.
Wrote and modified computer programs (e.g., RELAP and CONTEMPT) related to nuclear safety. The areas of focus included boiling water reactor loss of coolant accident analysis, pipe rupture loads and effects, building pressurization and hydraulic loads resulting from valve closure.
Wrote and modified computer programs (e.g., RELAP and CONTEMPT) related to nuclear safety. The areas of focus included boiling water reactor loss of coolant accident analysis, pipe rupture loads and effects, building pressurization and hydraulic loads resulting from valve closure.
REFERENCES Professional and personal references available on request.
1972-1973 REFERENCES Professional and EDUCATION ScD Mech Eng MS BSME personal references available on request.
EDUCATION ScD        Mechanical Engineering, Massachusetts Institute of Technology, Cambridge, MA 02139, 1972 Mech Eng    Mechanical Engineering, Massachusetts Institute of Technology, 1968 MS          Mechanical Engineering, Massachusetts Institute of Technology, 1968 BSME        Mechanical Engineering, Magna Cum Laude, New Jersey Institute of Technology, Newark, NJ 07102, 1966 Bayonne High School, Bayonne, New Jersey 07002 HONORS American Nuclear Society, Fellow American Society of Mechanical Engineers, Fellow Sigma Xi (Honorary Scientific Research Society)
Mechanical Engineering, Massachusetts Institute of Technology, Cambridge, MA 02139, 1972 Mechanical Engineering, Massachusetts Institute of Technology, 1968 Mechanical Engineering, Massachusetts Institute of Technology, 1968 Mechanical Engineering, Magna Cum Laude, New Jersey Institute of Technology, Newark, NJ 07102, 1966 Bayonne High School, Bayonne, New Jersey 07002 HONORS American Nuclear Society, Fellow American Society of Mechanical Engineers, Fellow Sigma Xi (Honorary Scientific Research Society)
National Science Foundation Graduate Fellowship Tau Beta Pi (Engineering Honor Society) 2
National Science Foundation Graduate Fellowship Tau Beta Pi (Engineering Honor Society) 2


Line 42: Line 46:
Pi Thu Sigma (National Mechanical Engineering Honor Society)
Pi Thu Sigma (National Mechanical Engineering Honor Society)
Honors on Admission, New Jersey Institute of Technology PATENTS AND PUBLICATIONS U.S. Patent - Patent Number 4,372,376, Heat Pump Apparatus, February 8, 1983.
Honors on Admission, New Jersey Institute of Technology PATENTS AND PUBLICATIONS U.S. Patent - Patent Number 4,372,376, Heat Pump Apparatus, February 8, 1983.
Books Co-author of the EPRI book, PressureDrop Technology for Design andAnalysis, published 1999.
Books Co-author of the EPRI book, Pressure Drop Technology for Design and Analysis, published 1999.
Co-author of the EPRI book, Flow-Accelerated Corrosionin Power Plants, published 1996 and revised in 1998.
Co-author of the EPRI book, Flow-Accelerated Corrosion in Power Plants, published 1996 and revised in 1998.
Co-author of the EPRI book, Void FractionTechnology for Design and Analysis, published 1997.
Co-author of the EPRI book, Void Fraction Technology for Design and Analysis, published 1997.
PublishedRepokts - sole author of the following EPRI Reports Development of an Averaged Point-to-PointMethodfor Inspection Data, EPRI, Palo Alto, CA, to be published.
PublishedRepokts - sole author of the following EPRI Reports Development of an Averaged Point-to-Point Method for Inspection Data, EPRI, Palo Alto, CA, to be published.
Investigation into CombiningSingle and Multiple Outage Inspection Data, EPRI, Palo Alto, CA, to be published.
Investigation into Combining Single and Multiple Outage Inspection Data, EPRI, Palo Alto, CA, to be published.
Development of a Figureof Meritfor EvaluatingCHECWORKSrM SFA Pass 2 Results, EPRI, Palo Alto, CA, to be published.
Development of a Figure of Merit for Evaluating CHECWORKSrM SFA Pass 2 Results, EPRI, Palo Alto, CA, to be published.
Investigation into Flow-Accelerated Corrosionat Low Temperatures,EPRI Report, 1013474, November 2007.
Investigation into Flow-Accelerated Corrosion at Low Temperatures, EPRI Report, 1013474, November 2007.
Flow-AcceleratedCorrosion- The EntranceEffect, EPRI Report, 1015072, November 2007.
Flow-Accelerated Corrosion - The Entrance Effect, EPRI Report, 1015072, November 2007.
Interim Recommendationsfor an Effective Program againstErosive Attack, EPRI Report, 101507, December 2007.
Interim Recommendations for an Effective Program against Erosive Attack, EPRI Report, 101507, December 2007.
Investigationinto Flow-AcceleratedCorrosion at Low Temperatures, EPRI Report, 1013474, November 2006.
Investigation into Flow-Accelerated Corrosion at Low Temperatures, EPRI Report, 1013474, November 2006.
Computer-BasedTrainingModule on Erosion in PipingSystems, EPRI Report 1013570, November 2006.
Computer-Based Training Module on Erosion in Piping Systems, EPRI Report 1013570, November 2006.
Computer Based TrainingModule on Flow-Accelerated Corrosion(FA C)for non-FAC Personnel,EPRI Report 1013249, May 2006.
Computer Based Training Module on Flow-Accelerated Corrosion (FA C)for non-FAC Personnel, EPRI Report 1013249, May 2006.
DeterminingPiping Wear Causedby Flow-AcceleratedCorrosionfrom Single-Outage Inspection Data, EPRI Report 1013012, March 2006.
Determining Piping Wear Caused by Flow-Accelerated Corrosion from Single-Outage Inspection Data, EPRI Report 1013012, March 2006.
3
3


An Evaluation of Flow-AcceleratedCorrosionin the Bottom HeadDrainLines of Boiling Water Reactors,EPRI Report 1013013, March 2006.
An Evaluation of Flow-Accelerated Corrosion in the Bottom Head Drain Lines of Boiling Water Reactors, EPRI Report 1013013, March 2006.
Chemistry Effects on Flow-AcceleratedCorrosion- PWR: Hydrazine and Oxygen Investigations,EPRI Report 1011835, November 2005.
Chemistry Effects on Flow-Accelerated Corrosion - PWR: Hydrazine and Oxygen Investigations, EPRI Report 1011835, November 2005.
Chemistry Effects on Flow-AcceleratedCorrosion- B WR: Dissolved Oxygen Investigation,EPRI Report 1011833, November 2005.
Chemistry Effects on Flow-Accelerated Corrosion - B WR: Dissolved Oxygen Investigation, EPRI Report 1011833, November 2005.
Recommendations for Controlling Cavitation, Flashing,LiquidDroplet Impingement, and Solid ParticleErosion in Nuclear Power PlantPiping Systems, EPRI Report 1011231, November 2004.
Recommendations for Controlling Cavitation, Flashing, Liquid Droplet Impingement, and Solid Particle Erosion in Nuclear Power Plant Piping Systems, EPRI Report 1011231, November 2004.
Flow-AcceleratedCorrosionInvestigations of Trace Chromium, EPRI Report 1008047, November 2003.
Flow-Accelerated Corrosion Investigations of Trace Chromium, EPRI Report 1008047, November 2003.
Selective Attack of Welds by Flow-Accelerated Corrosion,EPRI Report 1007057, July 2002.
Selective Attack of Welds by Flow-Accelerated Corrosion, EPRI Report 1007057, July 2002.
Published Reports - co-author of the following EPRI Reports Recommendationsfor an Effective Flow-Accelerated'CorrosionProgram(NSA C-202L-R3), Non-ProprietaryVersion, EPRI, Palo Alto, CA: 2007. 1015425.
Published Reports - co-author of the following EPRI Reports Recommendations for an Effective Flow-Accelerated'Corrosion Program (NSA C-202L-R3), Non-Proprietary Version, EPRI, Palo Alto, CA: 2007. 1015425.
Recommendationsfor an Effective Flow-Accelerated CorrosionProgram(NSA C-202L-R3), EPRI Report 1011838, May 2006.
Recommendations for an Effective Flow-Accelerated Corrosion Program (NSA C-202L-R3), EPRI Report 1011838, May 2006.
Recommendationsfor an Effective Flow-Accelerated CorrosionProgram,NSAC-202L, Revision 2, April 1999.
Recommendations for an Effective Flow-Accelerated Corrosion Program, NSAC-202L, Revision 2, April 1999.
CHECUPTM , a CHECWORKSrM Application for FAC Evaluation of Fossil Power Plants- Users Guide, EPRI TR-103198-P5, November 1998.
CHECUPTM, a CHECWORKSrM Application for FAC Evaluation of Fossil Power Plants - Users Guide, EPRI TR-103198-P5, November 1998.
CHECWORKSrM Computer Program Users Guide, EPRI TR- 103198-P 1, December 1997.
CHECWORKSrM Computer Program Users Guide, EPRI TR-103198-P 1, December 1997.
Guidelinesfor ControllingFlow-Accelerated Corrosionin Fossil Plants, EPRI TR-108859, November 1997.
Guidelines for Controlling Flow-Accelerated Corrosion in Fossil Plants, EPRI TR-108859, November 1997.
Recommendationsfor an Effective Flow-AcceleratedCorrosion Program,NSAC-202L, Revision 1, January 1997.
Recommendations for an Effective Flow-Accelerated Corrosion Program, NSAC-202L, Revision 1, January 1997.
Understanding Void Fractionin Steady State and Dynamic Environments, EPRI TR-106326, August 1996.
Understanding Void Fraction in Steady State and Dynamic Environments, EPRI TR-106326, August 1996.
Recommendationsfor an Effective Flow-AcceleratedCorrosionProgram,NSAC-202L, November 1993.
Recommendations for an Effective Flow-Accelerated Corrosion Program, NSAC-202L, November 1993.
An Analysis of BWR Fuel Heatup During a Loss of Coolant While Refueling, NSAC-169, November 1991.
An Analysis of BWR Fuel Heatup During a Loss of Coolant While Refueling, NSAC-169, November 1991.
CHEC-NDErm a Tool for Managing Non-Destructive EvaluationDatafrom Pipe Inspections, EPRI NP-7017-CCML, NSAC- 149L, April 1991.
CHEC-NDErm a Tool for Managing Non-Destructive Evaluation Data from Pipe Inspections, EPRI NP-7017-CCML, NSAC-1 49L, April 1991.
CHECMA TETM Computer Program Users Guide, NSAC-145L, Original May 1989, and Rev. 1, April 1991.
CHECMA TETM Computer Program Users Guide, NSAC-145L, Original May 1989, and Rev. 1, April 1991.
4
4


The Chexal-Lelouche Void FractionCorrelationfor GeneralizedApplications, NSAC-139, April 1991.
The Chexal-Lelouche Void Fraction Correlation for Generalized Applications, NSAC-139, April 1991.
CHECComputerProgram Users Manual,NSAC- 112L, Original July 1987 and Rev. 1, July 1989.
CHEC Computer Program Users Manual, NSAC-112L, Original July 1987 and Rev. 1, July 1989.
An Assessment of Eight Void FractionModels for Vertical Flows, NSAC-107, December 1986.
An Assessment of Eight Void Fraction Models for Vertical Flows, NSAC-107, December 1986.
A Full-RangeDrift-Flux Correlationfor Vertical Flows (Revision 1), EPRI NP-3989-SR, September 1986.
A Full-Range Drift-Flux Correlation for Vertical Flows (Revision 1), EPRI NP-3989-SR, September 1986.
Response of a B& W Plant to Steam GeneratorTube Ruptures, NSAC-101, September 1986.
Response of a B& W Plant to Steam Generator Tube Ruptures, NSAC-101, September 1986.
EPRIR&D Contributionsto the TechnicalBasis for Revision of ECCS Rules, EPRI NP-4146-SR, July 1985.
EPRIR&D Contributions to the Technical Basis for Revision of ECCS Rules, EPRI NP-4146-SR, July 1985.
Technical Papers - More than 45 published technical papers on nuclear safety analysis, thermal-hydraulics, and flow-accelerated corrosion.
Technical Papers - More than 45 published technical papers on nuclear safety analysis, thermal-hydraulics, and flow-accelerated corrosion.
5}}
5}}

Latest revision as of 15:15, 14 January 2025

July 2008 Evidentiary Hearing - Applicant Exhibit E4-02-VY, Horowitz Cv
ML082530272
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 07/23/2008
From: Horowitz J
- No Known Affiliation
To:
NRC/SECY/RAS
SECY RAS
References
06-849-03-LR, 50-271-LR, Entergy-Applicant-E4-02-VY, RAS M-317
Download: ML082530272 (5)
v • d • e


Text

/-Ac-S H-S 112 DOCKETED USNRC August 12, 2008 (11:00am)

OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF RESUME Jeffrey S. Horowitz, ScD PROFESSIONAL EXPERIENCE 1985 - Present Independent consultant working in the nuclear and mechanical engineering fields. Consultant to EPRI (Electric Power Research Institute) on single and two-phase flow-accelerated corrosion (also known as erosion-corrosion), cavitation, thermal-hydraulic analyses, void fraction correlation and service water corrosion.

Principal creator of CHEC, CHECMATE and CHECWORKS, the computer programs which predict single-phase and two-phase flow-accelerated corrosion. CHECWORKS is currently used to improve maintenance efficiency and enhance safety in more than 150 nuclear units worldwide.

Consultant to Arizona Public Service, the CANDU (Canadian Deuterium Uranium reactors) Owners Group, Exelon Corporation, Ontario Power Generation, Inc., Pacific Gas & Electric and Southern California Edison on issues of flow-accelerated corrosion and nuclear safety.

Co-author of three books and 34 published EPRI reports. Sole author of 16 published EPRI reports.

Program Manager, U.S. Department of Energy, 9800 South Cass Avenue, Argonne, Illinois, 60439, 630-252-2000, Frank Herbaty, supervisor:

Managed substantial portions of the Industrial Co-generation, Magneto-hydrodynamics (MHD) and Ocean Thermal Energy Conversion (OTEC)

Programs at the Chicago Operations Office. The annual value of the work I managed was about $10 million.

Promoted from GS-13 to GS-14.

1980-1984 1977 - 1980 Mechanical Engineer, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439, 630-252-2000. D..Norman Sather, supervisor:

IUULr.,-tl i~t3uLATfV IntheMatterof 5lLý¶> tjje jV.~j~j, i Oocket No,.,L...-.p Official Exhibit No.--"

-- U'f OIFFERED by4

ý)

t)FFERED by Intervenor NRC Staff Other IDENTIFIED) oni3&3 W2Iwinessmpanol-K FJC g Adton TakmW REJECTED W NIWN

1973-1977 Government Technical Manager on several, multi-million dollar OTEC power systems studies and heat exchanger construction programs.

Conducted design studies, computer modeling and laboratory testing on a metal-hydride heat pump system.

Promoted from Assistant Mechanical Engineer to Mechanical Engineer.

Principal Engineer, Combustion Engineering, 1000 Prospect Hill Road, Windsor, CT 06095, 860-688-1911, Dr. Hector Guerrero, supervisor:

Lead engineer on a series of nuclear safety experiments including tests on an alternate emergency core cooling system, steam generator depressurization, re-flood heat transfer and an innovative primary system flow meter.

Nuclear Engineer, Quadrex Corporation, 477 Division Street, Campbell, California, (company now defunct), Randolph Broman, supervisor:

Conducted various nuclear safety analyses.

Wrote and modified computer programs (e.g., RELAP and CONTEMPT) related to nuclear safety. The areas of focus included boiling water reactor loss of coolant accident analysis, pipe rupture loads and effects, building pressurization and hydraulic loads resulting from valve closure.

1972-1973 REFERENCES Professional and EDUCATION ScD Mech Eng MS BSME personal references available on request.

Mechanical Engineering, Massachusetts Institute of Technology, Cambridge, MA 02139, 1972 Mechanical Engineering, Massachusetts Institute of Technology, 1968 Mechanical Engineering, Massachusetts Institute of Technology, 1968 Mechanical Engineering, Magna Cum Laude, New Jersey Institute of Technology, Newark, NJ 07102, 1966 Bayonne High School, Bayonne, New Jersey 07002 HONORS American Nuclear Society, Fellow American Society of Mechanical Engineers, Fellow Sigma Xi (Honorary Scientific Research Society)

National Science Foundation Graduate Fellowship Tau Beta Pi (Engineering Honor Society) 2

(.

Pi Thu Sigma (National Mechanical Engineering Honor Society)

Honors on Admission, New Jersey Institute of Technology PATENTS AND PUBLICATIONS U.S. Patent - Patent Number 4,372,376, Heat Pump Apparatus, February 8, 1983.

Books Co-author of the EPRI book, Pressure Drop Technology for Design and Analysis, published 1999.

Co-author of the EPRI book, Flow-Accelerated Corrosion in Power Plants, published 1996 and revised in 1998.

Co-author of the EPRI book, Void Fraction Technology for Design and Analysis, published 1997.

PublishedRepokts - sole author of the following EPRI Reports Development of an Averaged Point-to-Point Method for Inspection Data, EPRI, Palo Alto, CA, to be published.

Investigation into Combining Single and Multiple Outage Inspection Data, EPRI, Palo Alto, CA, to be published.

Development of a Figure of Merit for Evaluating CHECWORKSrM SFA Pass 2 Results, EPRI, Palo Alto, CA, to be published.

Investigation into Flow-Accelerated Corrosion at Low Temperatures, EPRI Report, 1013474, November 2007.

Flow-Accelerated Corrosion - The Entrance Effect, EPRI Report, 1015072, November 2007.

Interim Recommendations for an Effective Program against Erosive Attack, EPRI Report, 101507, December 2007.

Investigation into Flow-Accelerated Corrosion at Low Temperatures, EPRI Report, 1013474, November 2006.

Computer-Based Training Module on Erosion in Piping Systems, EPRI Report 1013570, November 2006.

Computer Based Training Module on Flow-Accelerated Corrosion (FA C)for non-FAC Personnel, EPRI Report 1013249, May 2006.

Determining Piping Wear Caused by Flow-Accelerated Corrosion from Single-Outage Inspection Data, EPRI Report 1013012, March 2006.

3

An Evaluation of Flow-Accelerated Corrosion in the Bottom Head Drain Lines of Boiling Water Reactors, EPRI Report 1013013, March 2006.

Chemistry Effects on Flow-Accelerated Corrosion - PWR: Hydrazine and Oxygen Investigations, EPRI Report 1011835, November 2005.

Chemistry Effects on Flow-Accelerated Corrosion - B WR: Dissolved Oxygen Investigation, EPRI Report 1011833, November 2005.

Recommendations for Controlling Cavitation, Flashing, Liquid Droplet Impingement, and Solid Particle Erosion in Nuclear Power Plant Piping Systems, EPRI Report 1011231, November 2004.

Flow-Accelerated Corrosion Investigations of Trace Chromium, EPRI Report 1008047, November 2003.

Selective Attack of Welds by Flow-Accelerated Corrosion, EPRI Report 1007057, July 2002.

Published Reports - co-author of the following EPRI Reports Recommendations for an Effective Flow-Accelerated'Corrosion Program (NSA C-202L-R3), Non-Proprietary Version, EPRI, Palo Alto, CA: 2007. 1015425.

Recommendations for an Effective Flow-Accelerated Corrosion Program (NSA C-202L-R3), EPRI Report 1011838, May 2006.

Recommendations for an Effective Flow-Accelerated Corrosion Program, NSAC-202L, Revision 2, April 1999.

CHECUPTM, a CHECWORKSrM Application for FAC Evaluation of Fossil Power Plants - Users Guide, EPRI TR-103198-P5, November 1998.

CHECWORKSrM Computer Program Users Guide, EPRI TR-103198-P 1, December 1997.

Guidelines for Controlling Flow-Accelerated Corrosion in Fossil Plants, EPRI TR-108859, November 1997.

Recommendations for an Effective Flow-Accelerated Corrosion Program, NSAC-202L, Revision 1, January 1997.

Understanding Void Fraction in Steady State and Dynamic Environments, EPRI TR-106326, August 1996.

Recommendations for an Effective Flow-Accelerated Corrosion Program, NSAC-202L, November 1993.

An Analysis of BWR Fuel Heatup During a Loss of Coolant While Refueling, NSAC-169, November 1991.

CHEC-NDErm a Tool for Managing Non-Destructive Evaluation Data from Pipe Inspections, EPRI NP-7017-CCML, NSAC-1 49L, April 1991.

CHECMA TETM Computer Program Users Guide, NSAC-145L, Original May 1989, and Rev. 1, April 1991.

4

The Chexal-Lelouche Void Fraction Correlation for Generalized Applications, NSAC-139, April 1991.

CHEC Computer Program Users Manual, NSAC-112L, Original July 1987 and Rev. 1, July 1989.

An Assessment of Eight Void Fraction Models for Vertical Flows, NSAC-107, December 1986.

A Full-Range Drift-Flux Correlation for Vertical Flows (Revision 1), EPRI NP-3989-SR, September 1986.

Response of a B& W Plant to Steam Generator Tube Ruptures, NSAC-101, September 1986.

EPRIR&D Contributions to the Technical Basis for Revision of ECCS Rules, EPRI NP-4146-SR, July 1985.

Technical Papers - More than 45 published technical papers on nuclear safety analysis, thermal-hydraulics, and flow-accelerated corrosion.

5

Retrieved from "https://kanterella.com/w/index.php?title=ML082530272&oldid=5326132"