Our primary focus as a R&D company is on the development of innovative structural integrity solutions that replicate “real world” behavior for the oil/gas and nuclear energy industries. We are both nationally and internationally recognized experts fracture mechanics, weld process modeling, safety assessments and risk analysis of complex engineered systems and structures. Our work has often been ground-breaking in nature and has been cited in the past when industry codes and standards are updated.

As a result of these past program successes, our staff routinely has the opportunity to publish their results and present them at conferences or have it included in technical journals. As a company, we have collectively published as many as twenty-five (25) technical papers in a single year and have averaged twenty (20) publications each year since 2007. To date, our staff members have published over 220 technical papers or journal articles since our founding in 1998 and the number of papers grows to over 500 when you factor in the publications from our staff members prior to their joining Emc2.

We are in the process of updating our list. the most recent papers can be found below, sorted by years. We will continue to update this list to add future work and complete the missing years

If you are looking for information on a particular topic and don’t see it here, please contact Mr. Gary Hattery at ghattery@emc-sq.com or Dr. Gery Wilkowski at gwilkows@emc-sq.com for further information.

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59 entries « 1 of 2 »

2016

Olson,; Kalyanam,; Park,; Brust,

Improvement of the LBB ENG2 Circumferential Through-wall Crack J-estimation Scheme Proceeding

ASME Proceedings of ASME Pressure Vessels & Piping Conference, Vancouver, British Columbia, Canada, PVp2016 (63264), 2016.

BibTeX | Tags: Ductile Fracture, Elastic-plastic Fracture, Failure Criterion, LBB, Nuclear

Kalyanam,; Brust,; Wilkowski,; Shim,; Rudland,

Validation of Axial Crack Stability Assessment Methods in xLPR Version 2.0 Code Proceeding

Proceedings of ASME Pressure Vessels & Piping Conference, PVP2016 (63830), 2016.

BibTeX | Tags: Axial Crack, Charpy, Crack Stability, Elastic-plastic Fracture, Failure Criterion, Fracture Toughness, Nuclear, xLPR

Uddin,; Kurth,; Sallaberry,; Wilkowski,; Brust,; Rudland,

Critical Flaw Evaluation of Cast Austenitic Stainless Steel: Deterministic and Probabilistic Fracture Analyses Proceeding

Proceedings of ASME Pressure Vessels & Piping Conference, Vancouver, British Columbia, Canada, PVP2016 (63850), 2016.

BibTeX | Tags: CASS, Fracture, Fracture Toughness, Nuclear, Probability

Wilkowski,; Brust,; Uddin,; Kalyanam,; Lacroix,

Evaluation of the Lowest Temperature for Ductile Crack Initiation in an Irradiated RPV Proceeding

ASME Proceedings of ASME Pressure Vessels & Piping Conference, Vancouver, British Columbia, Canada, PVP2016 (63593), 2016.

BibTeX | Tags: Ductile Fracture, Failure Criterion, FITT, Fracture Toughness, Nuclear

2015

Shim,; Wallace,; Kalyanam,; Benson,

Validation of Stress Intensity Factor Solutions in xLPR Version 2.0 Code Proceeding

Proceedings of ASME Pressure Vessels & Piping Conference, Boston MA, PVP2015 (45575), 2015.

BibTeX | Tags: Axial Crack, Circumferential Crack, LBB, Nuclear, PWSCC, SIF, xLPR

Uddin,; Wilkowski,; Brust,; Shim,; Rudland,

Comparison of Different Thermal Aging Models to Assess Fully Ages Toughness in Cast Austenitic Stainless Steels Proceeding

Proceedings of ASME Pressure Vessels & Piping Conference, Boston MA, PVP2015 (45790), 2015.

BibTeX | Tags: CASS, Fracture Toughness, Nuclear

Uddin,; Kurth-Twombly,; Brust,; Wilkowski,; Betervide,; Mazzantini,; Fernandez,

Prediction of Dynamic Break-Opening Area under Beyond Design Basis Seismic Loading Proceeding

Proceedings of ASME Pressure Vessels & Piping Conference, Boston MA, PVP2015 (45156), 2015.

BibTeX | Tags: Ductile Fracture, Dynamic Crack Propagation, Elastic-plastic Fracture, Fracture Toughness, Nuclear

Kurth,; Wilkowski,; Shim,; Brust,

Probabilistic Procedure for Critical Flaw Evaluation of Cass Using Actual Toughness Distribution Proceeding

Proceedings of ASME Pressure Vessels & Piping Conference, Boston MA, PVP2015 (45794), 2015.

BibTeX | Tags: Axial Crack, CASS, Circumferential Crack, Fracture Toughness, Nuclear, Probability

Kalyanam,; Krishnaswamy,; Hioe,; Shim,; Focht,

A Fracture Mechanics Approach to Service Life Prediction of HDPE Fusion Joints in Nuclear Applications Proceeding

Proceedings of SPE, ANTEC, Orlando, FL, 2015.

BibTeX | Tags: Fracture, HDPE, Nuclear, Plastics, SENT, Slow Crack Growth

2014

Shim,; Xu,; Kerr,

Effect of Weld Residual Stress Fitting on Stress Intensity Factor for Circumferential Surface Cracks in Pipes Journal Article

J. Pressure Vessel Technology, 137 (1), pp. 011403, 2014.

BibTeX | Tags: Circumferential Crack, Nuclear, PWSCC, SIF, Welds, WRS, xLPR

2013

Shim,; Han,; Huh,

Finite Element Loads for Non-Idealized Through-Wall Cracks in Thick-Walled Pipe Journal Article

Nuclear Engineering and Design, 265 , pp. 918-931, 2013.

BibTeX | Tags: FEA, Nuclear, TWC

Shim,

Recent Developments in Deterministic LBB Analysis Methods for Probabilistic Assessment Applications Presentation

25.10.2013.

BibTeX | Tags: LBB, Nuclear, Probability

Brust,; Shim,; Wilkowski,

Effects of Weld Repairs on Natural Flaw Growth and Crack Stability in Nuclear Piping Proceeding

American Society for Metals (ASM) Meeting, 2013.

BibTeX | Tags: Crack Stability, Nuclear

2012

Krishnaswamy,; Kalyanam,; Hioe,; Shim,

A Methodology to Predict Critical Flaw Size in HDPE Piping and Joints in Nuclear Safety-Related Applications Presentation

26.09.2012.

BibTeX | Tags: HDPE, Nuclear

Zhang,; Brust,; Wilkowski,; Xu,; Betervide,; Mazzantini,

Beyond Design Basis Seismic Analysis for Atucha II Nuclear Plant Proceeding

Proceedings of the 20th International Conference on Nuclear Engineering , (ICONE20POWER2012-54241), 2012.

BibTeX | Tags: Nuclear

Kalyanam,; Krishnaswamy,; Shim,; Hioe,; Focht,

Structural Integrity of HDPE Piping and Joints in Nuclear Safety-Related Applications Proceeding

20th International Conference on Nuclear Engineering, (ICONE20-54192), 2012.

BibTeX | Tags: HDPE, Nuclear

Zhang,; Brust,; Wilkowski,; Xu,

Welding Residual Stress in A Large Diameter Nuclear Reactor Pressure Vessel Nozzle Proceeding

Proceedings of the ASME 2012 Pressure Vessels & Piping Conference, (PVP2012-78578), 2012.

BibTeX | Tags: Nuclear, WRS

Zhang,; Brust,; Wilkowski,; Shim,; Nie,; Hofmayer,; Ali,

Numerical Analysis of JNES Seismic Tests on Degraded Combined Piping System Journal Article

Journal of Pressure Vessel Technology, 134 (1), pp. 011801, 2012.

BibTeX | Tags: Nuclear, Numerical Analysis

2011

Helton,; Johnson,; Sallaberry,

Quantification of margins and uncertainties: example analyses from reactor safety and radioactive waste disposal involving the separation of aleatory and epistemic uncertainty Journal Article

Reliability Engineering & System Safety, 96 (9), pp. 1014-1033, 2011.

BibTeX | Tags: aleatory, epistemic, Nuclear, nuclear waste

Wilkowski,; Brust,; Krishnaswamy,; Wichman,; Shim,; Rudland,

Lesson Learned For Nuclear Piping Integrity in New Reactors Proceeding

Proceedings of the ASME 2011 Pressure Vessels & Piping Division Conference, (PVP2011-57941), 2011.

BibTeX | Tags: Nuclear

Kalyanam,; Shim,; Hioe,; Krishnaswamy,

Slow Crack Growth Resistance of Parent and Joint Materials from PE4710 Piping for Safety-Related Nuclear Power Plant Piping Proceeding

Proceedings of the ASME 2011 Pressure Vessels & Piping Division Conference, (PVP2011-57874), 2011.

BibTeX | Tags: Nuclear

Kalyanam,; Krishnaswamy,; Uddin,; Shim,

A Simplified Stress Intensity Factor Relation for Assessment of External Axial Flawed Safety-Related Nuclear Power Plant HDPE Piping Proceeding

Proceedings of the ASME 2011 Pressure Vessels & Piping Division Conference, (PVP2011-57904), 2011.

BibTeX | Tags: Axial Crack, HDPE, Nuclear, SIF

2010

Mattie,; Sallaberry,; Helton,; Kalinich,

Development, Analysis, and Evaluation of a Commercial Software Framework for the Study of Extremely Low Probability of Rupture (xLPR) Events at Nuclear Power Plants Technical Report

Sandia National Laboratories (SAND2010-8480), 2010.

BibTeX | Tags: Nuclear, xLPR

Mattie,; Kalinich,; Sallaberry,

US Nuclear Regulatory Commission Extremely Low Probability of Rupture Pilot Study: xLPR Framework Model User's Guide Technical Report

Sandia National Laboratories (SAND2010-7131), 2010.

BibTeX | Tags: Nuclear, Probability, xLPR

Shim,; Krishnaswamy,; Kalyanam,; Hioe,

Viscoelastic Finite Element Modeling of Bimodal High Density Polyethylene (HDPE) Piping Materials for Nuclear Safety-Related Applications Proceeding

Proceedings of the ASME 2010 Pressure Vessels & Piping Division Conference, (PVP2010-25715), 2010.

BibTeX | Tags: FEA, HDPE, Nuclear

Zhang,; Brust,; Wilkowski,; Ranganath,; Tsai,; Huang,; Liu,

Weld Residual Stress Analysis and the Effects of Structural Overlay on Various Nuclear Power Plant Nozzles Proceeding

Proceedings of the ASME 2010 Pressure Vessels & Piping Division Conference, (PVP2010‑25331), 2010.

BibTeX | Tags: Nuclear, weld overlay, WRS

Krishnaswamy,; Shim,

A Review of Service Life Prediction Models for Polyethylene Piping for Nuclear Safety-Related Applications Presentation

01.01.2010.

BibTeX | Tags: Nuclear, Plastics

2009

Fredette,; Scott,; Brust,

An Analytical Evaluation of the Effect of Weld Material Thickness on Residual Stresses Produced by Structural Weld Overlays on Pressurized Water Reactor Primary Coolant Piping Proceeding

Proceedings of the ASME 2009 Pressure Vessels & Piping Division Conference, (PVP2009-77330), 2009.

BibTeX | Tags: modeling, Nuclear, weld overlay, WRS

Fredette,; Scott,; Brust,

An Analytical Evaluation of the Effect of Full Structural Weld Overlay as a Stress Improving Mitigation Strategy to Prevent Primary Water Stress Corrosion Cracking in Pressurized Water Reactor Piping Proceeding

Proceedings of the ASME 2009 Pressure Vessels & Piping Division Conference, (PVP2009-77327), 2009.

BibTeX | Tags: modeling, Nuclear, PWSCC, weld overlay

2008

Rudland,; Zhang,; Wilkowski,; Csontos,

Welding Residual Stress Solutions for Dissimilar Metal Surge Line Nozzles Welds Proceeding

Proceedings of the ASME 2008 Pressure Vessels & Piping Division Conference, (PVP2008-61285), 2008.

BibTeX | Tags: DMW, Nuclear, WRS

Bamford,; Cipolla,; Rudland,; Deboo,

Technical Basis for Revisions to IWB 3640 for Alloy 600/82/182 Flaw Evaluation in both PWR and BWR Environments Proceeding

Proceedings of the ASME 2008 Pressure Vessels & Piping Division Conference, (PVP2008-61840), 2008.

BibTeX | Tags: Nuclear

2006

Rudland,; Xu,; Wilkowski,; Scott,; Ghadiali,; Brust,

Development of a New Generation Computer Code (PRO-LOCA) for the Prediction of Break Probabilities for Commercial Nuclear Power Plants Loss-Of-Coolant Accidents Proceeding

Proceedings of the ASME 2006 Pressure Vessels & Piping Division Conference, (PVP2006-ICPVT11-93802), 2006.

BibTeX | Tags: LBB, Nuclear, PFM

Xu,; Rudland,; Wilkowski,; Scott,

Statistical Characteristics Analysis and Simulation of Circumferential IGSCC Cracks for a BWR Plant Proceeding

Proceedings of the ASME 2006 Pressure Vessels & Piping Division Conference, (PVP2006-ICPVT11-93966), 2006.

BibTeX | Tags: Circumferential Crack, Nuclear, statistics

2003

Scott,; Olson,; Wilkowski,; Santos,

Development of the Technical Basis for a New Regulatory Guide Proceeding

Proceedings of the 17th SMiRT Conference, 2003.

BibTeX | Tags: Nuclear

2002

Feng,; Wilkowski,

Repair Welding Of Irradiated Materials – Modeling Of Helium Bubble Distributions For Determining Crack-Free Welding Procedures Proceeding

Proceedings of ICONE-10 conference, 2002.

BibTeX | Tags: Nuclear, Welds

2001

Scott,; Olson,; Wilkowski,; Miura,; Choi,; Chang,; Chokshi,

Overview of the Battelle Integrity of Nuclear Piping (BINP) Program Presentation

01.08.2001.

BibTeX | Tags: Nuclear

2000

Brust,; Dong,

Welding Residual Stresses and Effects on Fracture in Pressure Vessel and Piping Components: A Millennium Review and Beyond Journal Article

Journal of Pressure Vessel Technology, 122 (3), pp. 329-339, 2000.

BibTeX | Tags: Nuclear, WRS

1999

Chopra,; Chung,; Kassner,; Park,; Shack,; Zhang,; Brust,; Dong,

Current Research on Environmentally Assisted Cracking in Light Water Reactor Environments Journal Article

Nuclear Engineering and Design, 194 (2-3), pp. 205-223, 1999.

BibTeX | Tags: Fracture, Nuclear

1997

Choi,; Lee,; Wilkowski,

Development of new Z-factors for the Evaluation of a Surface Crack in Nuclear Piping Proceeding

SMiRT-14 Proceedings, G (pp. 603-610), 1997.

BibTeX | Tags: Fracture, Nuclear

Rudland,; Wilkowski,

Toughness Trends under Dynamic and Cyclic Loading on Nuclear Piping Steels Proceeding

SMiRT-14 Proceedings, G (pp. 151-158), 1997.

BibTeX | Tags: Fracture Toughness, Nuclear

1996

Ghadiali,; Wilkowski,

Fracture Mechanics Database for Nuclear Piping Materials (PIFRAC) Proceeding

Proceedings of the ASME 1996 Pressure Vessels & Piping Division Conference, 324 (pp 77-84), 1996.

BibTeX | Tags: Fracture, Nuclear

Zhao,; Wilkowski,

A Case Study for Assessment of Consistency Between ASME Section III and Section XI Rules Proceeding

Proceedings of the ASME 1996 Pressure Vessels & Piping Division Conference, 340 (pp 331-344), 1996.

BibTeX | Tags: Line-pipe, Nuclear

Rahman,; Olson,; Rosenfield,; Wilkowski,

Summary of Results from the IPIRG 2 Round-Robin Analyses Technical Report

Nuclear Regulatory Commission (NUREG/CR-6337), 1996.

BibTeX | Tags: Line-pipe, Nuclear

1995

Mohan,; Marschall,; Krishnaswamy,; Krishna,; Ghadiali,; Wilkowski,

Effects of Toughness Anisotropy and Combined Tension, Torsion, and Bending Loads on Fracture Behavior of Ferritic Nuclear Pipe Proceeding

Proceedings of the LBB 95 conference in Lyon (France), 1995.

BibTeX | Tags: Fracture Toughness, Nuclear

Rahman,; Ghadiali,; Wilkowski,; Paul,

A Computer Model for Probabilistic Leak-Rate Analysis of Nuclear Piping and Piping Welds Proceeding

Proceedings of the ASME 1995 Pressure Vessels & Piping Division Conference, 1995.

BibTeX | Tags: leak rate, Nuclear, probabilistic, Welds

Scott,; Francini,; Rahman,; Rosenfield,; Wilkowski,

Fracture Evaluations of Fusion-Line Cracks in Nuclear Pipe Bimetallic Welds Technical Report

Nuclear Regulatory Commission (NUREG/CR-6297), 1995.

BibTeX | Tags: DMW, Fracture, Nuclear

Mohan,; Marschall,; Krishnaswamy,; Brust,; Ghadiali,; Wilkowski,

Effects of Toughness Anisotropy and Combined Loading on Fracture Behavior of Ferritic Nuclear Pipe Technical Report

Nuclear Regulatory Commission (NUREG/CR-6299), 1995.

BibTeX | Tags: Fracture Toughness, Nuclear

1994

Marschall,; Mohan,; Krishnaswamy,; Wilkowski,

Effect of Dynamic Strain Aging on the Strength and Toughness of Nuclear Ferritic Piping at LWR Temperatures Technical Report

Nuclear Regulatory Commission (NUREG/CR-6226), 1994.

BibTeX | Tags: Fracture Toughness, Nuclear

Marschall,; Rosenfield,; Held,; Wilkowski,

A Screening Criterion for Dynamic Strain Aging Sensitivity of Ferritic Nuclear Piping Steels Proceeding

280 (pp. 199-206), 1994.

BibTeX | Tags: Dynamic Crack Propagation, Nuclear

Olson,; Wolterman,; Wilkowski,

Margins for Dynamic FEM Analysis of Cracked Pipe Under Seismic Loading for the DOE New Production Reactor Proceeding

Proceedings of the ASME 1994 Pressure Vessels & Piping Division Conference, 280 (pp. 119-134), 1994.

BibTeX | Tags: Dynamic Crack Propagation, FEA, Nuclear, seismic loads

59 entries « 1 of 2 »