Dr. Kris Singh

President & Chief Executive Officer

Download Bio

Dr. Kris Singh is the Founder, President and CEO of Holtec International, which he established in 1986 and nurtured its steady rise into a multi-national company with its business footprint in eighteen countries on five continents. He is also a Professor at the University of South Florida’s (USF) Institute for Advanced Discovery and Innovation where he collaborates with the USF faculty in the areas of advanced thermal storage and efficient harnessing of solar energy.

Dr. Singh received his Ph.D. in Mechanical Engineering from the University of Pennsylvania, Philadelphia (1972), a Master of Science in Engineering Mechanics also from Penn (1969), and a Bachelor of Science in Mechanical Engineering from BIT Sindri (Ranchi University), India (1967). Dr. Singh was elected to the National Academy of Engineering in 2013 for his seminal impact in the energy sector of mechanical engineering. He received Edison Foundation’s “Thomas Alva Edison Award” in 2015 for his ecologically and environmentally impactful inventions. Rutgers University named him “South Jerseyan of the year – 2016” for his significant beneficial impact on the region. In 2015, he received the George Washington medal from the Engineer’s Club of Philadelphia. In 2017, the National Academy of Inventers elected him a Fellow and the University City Science Center (Philadelphia) inducted him into its “Walk of Fame” on the Penn campus. The Pan American Academy of Engineering, the Americas’ institution of leading engineering thought leaders, elected Dr. Singh to its Academy in 2020. In 2019, he was elected to the Academy of Science, Engineering and Medicine of Florida. He was named a Fellow of the American Society of Mechanical Engineers in 1987 for his numerous contributions to heat exchange technologies. He is an overseer of the nuclear engineering department at the University of California, Berkeley, and a senior fellow in Mechanical Engineering at the University of Pennsylvania. He is a registered Professional Engineer in Pennsylvania and Michigan and a member of the American Nuclear Society.

A widely published author in scientific journals (74 technical papers, one textbook and numerous symposia volumes) and a prolific inventor (170 patents granted in the US plus a large number overseas, many patents pending), Dr. Singh has led Holtec International into the distinguished rank of civilian nuclear industry’s only turnkey supplier in the nuclear and renewable energy sector with four operating manufacturing facilities making the Company one of the world’s largest provider of custom-engineered equipment and systems. Thanks to its impeccable performance record, Holtec is globally respected for its engineered goods and services with nine major operations centers serving clients on five continents. Over 140 nuclear plants around the world employ Holtec’s systems and equipment, many based on Dr. Singh’s patents. Thanks to the steady stream of design innovations, Holtec is widely held to be globally pre-eminent in the management of used nuclear fuel.

Several national and international codes and standards on pressure vessels and heat exchangers bear the imprint of Dr. Singh’s applied research. In recent years, Dr. Singh has been leading Holtec in the global race to develop a “walk away safe” small modular reactor to make nuclear energy a cost-competitive clean energy solution for a world struggling with rising carbon emissions. Under Dr. Singh’s leadership, Holtec is in the vanguard of emerging field and challenges such as cloud-based information management of all Company operations, development of cutting-edge manufacturing processes & machines, devising innovative technologies to decarbonize global economies, and applying Holtec’s innovative below-the-ground interim storage technology to solve America’s used nuclear fuel conundrum.

He is also a passionate sponsor of expedited regulatory acceptance, construction, and commissioning of the Company’s transformative, “walk away safe” small modular reactor, SMR-160 which (substantially self-funded by the Company) has been in development for over a decade with expected first deployment in 2029.

Ensuring an environmentally safe decommissioning of nuclear units after their shutdown using the Holtec’s Decommissioning Management Model which has been instrumental in enhancing the safety of the Company’s fleet of shuttered plants is of a piece with Dr. Singh’s modus operandi which is to expand the technology envelope in every industrial sector where Holtec operates. His most recent technology endeavor is to repurpose the retiring coal fired plants (instead of demolishing them) by converting them into energy storage and on-demand clean power delivery plants using Holtec’s patented “green boiler technology.” He is also working to integrate the Green Boiler energy storage technology with an advanced solar collection system to help make solar energy a base-load power provider.

An intrepid entrepreneur and a socially conscious industrialist, Dr. Singh built a $312 million Technology Campus on the Delaware River in Camden, NJ in 2017 to create much needed employment in one of America’s poorest cities.

Dr. Singh is currently an Emeritus member of the University of Pennsylvania’s Board of Trustees, where he served from 2009-2017, and is an active member of the Penn’s Board of Overseers for the School of Engineering and Applied Science. In addition, he serves on the Board of the Nuclear Energy Institute (1998-present), the Atlantic Council, a Washington, DC-based think tank, the “National Investment Council” chaired by the President of Ukraine and the Cooper Health System, Camden, NJ. He chairs the KPS Foundation, a charitable Singh family foundation whose signature contribution to the advancement of science is the completion of the “Krishna P. Singh Center for Nanotechnology” at the University of Pennsylvania in Philadelphia in 2013. The KPS Foundation is also active in improving child literacy and public health in developing countries.

Patents

TitleYearPatent No.Status
Radiation Shielded Enclosure for Spent Nuclear Fuel Cask2022US 11,521,761 B2Granted
Flow Baffles for Shell and Tube Heat Exchangers2022US 11,512,902 B2Granted
Nuclear Waste Storage Canisters, Welds, and Method of Fabricating the Same2022US 11,515,056 B2, CN ZL2016800621786Granted
Cooling System for Casks Containing High Level Nuclear Waste2022US 11,488,737 B2Granted
High-Density Subterranean Storage System for Nuclear Fuel and Radioactive Waste2022US 10,950,361 B2, US 10,446,287 B2, US 9,852,822 B2, US 11,469,008 B2Granted
Storage System for Radioactive Nuclear Waste with Pressure Surge Protection2022US 11,443,862 B2Granted
A Novel Impact Limiter Embodiment for Transport Casks for Radioactive Materials and a Thermal Shield Design to Protect the Cask’s Containment Seals during the Postulated Design Basis Fire Event2022Provisional
Passive Cooling Device for Casks Containing Nuclear Fuel2022US 11,410,784 B2Granted
Nuclear Reactor Vessel Support System2022US 11,393,598 B2, US 10,726,962 B2Granted
Ventilated Transfer Cask2022US 11,373,774 B2, US 10,811,154 B2, US 9,514,853 B2, US 8,905,259 B2, US 9,396,824, US 9,831,005, US 9,442,037, US 9,779,843, US 9,466,400Granted
Storage and Transport Cask for Nuclear Waste2022US 11,373,775 B2Granted
System and Methods for Storing Spent Nuclear Fuel2022US 9,916,911 B2, US 8,098,790, US 8,625,732, US 7,068,748, US 11,342,091 B2Granted
A Novel Technology to Convert Operating Fossil Burning Power Plants into Energy Storage and On-Demand Clean Power Generation Units202263/297,899Pending
A Device to Prevent Rattling of Free-Standing Components Under Earthquake or other Vibratory Loads202263/176,496Pending
Nuclear Reactor Shroud2022US 11,289,219 B2, US 9,773,576 B2, US 10,580,539 B2, EP 2 962 306 B1Granted
Nuclear Fuel Storage System with Integral Shimming2022US 11,289,229 B2Granted
Spent Nuclear Fuel Canister2022US 11,289,227 B2Granted
Spent Nuclear Fuel Cask with Dose Attenuation Devices2022US 11,282,615 B2Granted
Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment2022US 11,264,142 B2, US 10,614,924 B2, US 9,761,339 B2, US 8,718,220 B2, US 7,676,016Granted
Nuclear Fuel Storage Facility2022US 11,250,963 B2, US 10,373,722 B2,  US 9,443,625, US 8,351,562, US 7,933,374, US 7,330,526Granted
Manufacturing Methods to Fortify Nuclear Waste Canisters from Stress Corrosion Cracking2022US 11,250,962 B2Granted
Method for Preparing Spent Nuclear Fuel for Dry Storage2022US 11,217,353 B2, US 10,535,439 B2, US 9,761,338 B2, US 8,737,559 B2, US 8,266,823 B2, US 7,707,741 B2, EP 1 888 988 B1Granted
Air-Cooled Condenser System2021US 11,204,201 B2Granted
Heat Exchanger for Severe Service Conditions2021US 11,187,471 B2, CN ZL2018800462204Provisional
Fuel Storage Device with Prismatic Hexagonal or Rectangular Cross-Section Cells202163/271,849Pending
Steam Generator for Nuclear Steam Supply System2021US 11,120,920 B2, US 10,510,452, US 10,395,783 B2Granted
A Fail-Safe Control Rod Drive System for Nuclear Reactor2021US 11,094,421 B2, US 10,573,419 B2, US 10,573,418 B2, US 9,496,057Granted
Nuclear Waste Cask with Impact Protection2021US 11,081,249 B2Granted
Container for Storing And/Or Transporting Spent Nuclear Fuel2021US 11,081,248 B2, US 10,410,756 B2, EP 3264419, KR 10,2139794Granted
A System to Store Used Fuel Cannisters with Axial Ventilation For Heat Dissipation and Enhanced Shielding202163/271,849Pending
Multi-Component Cask for Storage and Transport of Spent Nuclear Fuel2021US 11,043,312 B2Granted
Method for Heating a Primary Coolant in a Nuclear Steam Supply System2021US 11,031,146 B2, US 10,102,936 B2Granted
System and Method for Minimizing Movement of Nuclear Fuel Racks During a Seismic Event2021US 11,017,908 B2, US 9,991,010 B2Granted
Stacked Column of Vertical Ventilated Modules to Store Canisters Contained Used Nuclear Fuel or High-Level Waste202163/189,383Pending
Vertical Ventilated Storage Module for High-Level Waste with Canisters Arrayed on Subterranean Support Pad202163/189,423Pending
Single-Plate Neutron Absorbing Apparatus and Method of Manufacturing the Same2021US 10,991,472 B2, US 8,681,924 B2, US 8,158,962 B1Granted
Harnessing Decay Heat Produced by Spent Nuclear Fuel Stored in Plant to Conserve Energy202163/178,000Pending
System for Low Profile Translation of High Level Radioactive Waste2021US 10,939,787 B2, US 10,446,285 B2, US 9,728,286 B2, US 8,345,813 B2Granted
Nuclear Fuel Core, Nuclear Fuel Cartridge, and Methods of Fueling and/or Defueling a Nuclear Reactor2021US 10,923,239 B2, US 9,865,363 B2Granted
Self-Aligning Neutron Absorbing Apparatus for Reactivity Mitigation in Nuclear Fuel Storage Systems2021US 10,910,119 B2, US 10,418,137 B2Granted
System and Method of Storing and/or Transferring High Level Radioactive Waste2021US 10,892,063 B2, US 9,831,005 B2Granted
Flood and Wind Resistant Ventilated Module for Storing Used Fuel Canisters2020US 10,878,973 B2Granted
Storage System for Nuclear Fuel2020US 10,867,714 B2, US 10,297,356 B2, US 9,640,289 B2, EP 3134900Granted
Apparatus for Storing and/or Transporting Radioactive Materials2020US 10,861,612 B2, US 10,515,730 B2Granted
Fuel Basket for Spent Nuclear Fuel and Container Implementing the Same2020US 10,854,346 B2, 10-2039918Granted
Air-Cooled Heat Exchanger and System and Method of Using the Same to Remove Waste Thermal Energy from Radioactive Materials2020US 10,854,344 B2, US 9,786,395 B2Granted
Macro-Chip Reinforced Alloy2020US 10,843,272 B2Granted
High Earthquake-Resistant Fuel Storage Rack System for Fuel Pools in Nuclear Plants2020US 10,847,274 B2, 10-2103451Granted
Deeply Imbedded Ventilate Storage (DTVS) System for Used Nuclear Fuel & High-Level Waste202063/123,706Provisional
System and Method for Preparing a Container Loaded with Wet Radioactive Elements for Dry Storage2020US 10,839,969 B2, US 8,561,318, US 9,165,690 B2, US 10,229,764 B2, EP 2 227 655 B1, EP 3 364 136 B1Granted
Passive Reactor Cooling System2020US 10,720,249 B2, US 9,589,685 B2, EP 2 842 135 B1, 6442489, EP 3 005 373 B1Granted
Method of Storing High Level Radioactive Waste2020US 10,714,223 B2Granted
Thermal Sleeve and Variable Vent Throttling to protect Used Fuel Bearing Canisters from Stress Corrosion Cracking in a Ventilated Storage System202063/043,812Pending
Container and System for Handling Damaged Nuclear Fuel, and Method of Making the Same2020US 10,692,617 B2, US 9,748,009 B2Granted
Component Cooling Water System for Nuclear Power Plant2020US 10,672,523 B2, US 9,786,394 B2Granted
Space Saver Flanged Joint for a Nuclear Reactor Vessel2020US 10,665,357 B2, US 9,892,806 B2Granted
Loss-of-Coolant Accident Reactor Cooling System2020US 10,665,354 B2, US 10,069,389 B2, JP 6454692, EP 3005374Granted
Rack for Underwater Storage of Spent Nuclear Fuel2020US 10,650,933 B2, CN ZL2015800601538, KR 10-232322, KR 10-2406322Granted
A Device for Cooling Fan Motors Used in Induced Draft Air Cooler Condensers202062/986,401Pending
Heavily Shielded Unventilated Cask for Storing Nuclear Waste202062/969,183Pending
An Impact Amelioration Device to Minimize Deceleration Loads from Colliding Hard Surfaces201962/954,083Pending
Brazing Compositions and Uses Thereof2019US 10,512,990 B2Granted
Autonomous self-powered system for removing thermal energy from pools of liquid heated by radioactive materials, and method of the same2019US 10,472,996 B2, US 9,803,510 B2Granted
Environmentally Sequestered Spent Fuel Pool2019US 10,468,145 B2, EP 3 204 949 B1, KR 10-1956628Granted
System and Method for Reclaiming Energy from Heat Emanating from Spent Nuclear Fuel2019US 10,418,136 B2, US 9,001,958 B2Granted
A Portable Robotic Welder201962/887,984Pending
Vertical Bundle Air Cooled Heat Exchanger, Method of Manufacturing the Same, and Power Generation Plant Implementing the Same2019US 10,343,240 B2, US 9,770,794 B2Granted
Apparatus for Storing and/or Transporting High Level Radioactive Waste, and Method for Manufacturing the Same2019US 10,332,642 B2Granted
Air Induced-Draft Air-Cooled Condenser Amenable to Efficient On-Site Assembly2019Provisional
Wet Storage Facility for Nuclear Fuel2019US 10,311,987 B2, EP 3 195 325 B1Granted
Tubular Heat Exchanger Having Multiple Shell-Side and Tube-Side Fluid Passes2019US 10,295,266 B2Granted
Dry Cooling System for Power Plants201810,161,683 B2Granted
Ventilated System for Storing High Level Radioactive Waste2018US 10,147,509 B2Granted
Shutdown System for a Nuclear Steam Supply System2018US 10,115,487 B2Granted
Apparatus for Supporting Spent Nuclear Fuel2018US 2018/0301231 A1, US 10,037,826 B2, CN 106663481Published
Method for Storing Radioactive Waste, and System for Implementing the Same2018US 10,049,777 B2Granted
Canister Apparatus for Dry Storage of Spent Nuclear Fuel and Method of Using the Same2018US 2018/0277273 A1, US 8,135,107 B2, US 8,929,504, 10,026,514 B2Published
Passively-Cooled Spent Nuclear Fuel Pool System2018US 2018/0277264 A1, US 10,008,296 B2, US 9,786,393, US 9,916,910 B2Published
Axi-Flow Baffle for Tubular Heat Exchangers201862/655,858Provisional
Nuclear Power Generation System2018US 9,922,740 B2Granted
Apparatus for Supporting Radioactive Fuel Assemblies and Methods for Manufacturing the Same2018US 2018/0025796 A1, US 9,728,284 B2, US 8,576,976 B2Published
A Reactivity Control Device for Storing Nuclear Fuel2018US 9,875,819 B2Granted
Nuclear Steam Supply System2017US 9,852,820 B2Granted
A Radioactive Material Storage Canister and Method for Sealing Same2017US 9,779,843 B2Granted
Treating the External Surface of Shell-Type Stainless Steel Structures to Protect Against Stress Corrosion Cracking201762/551,914Provisional
Cask Apparatus, System and Method for Transporting and/or Storing High Level Waste2017US 9,672,948 B2Granted
Heat Exchanger Apparatus for Converting a Shell-Side Liquid into a Vapor2017US 9,612,058 B2, US 8,833,437 B2Granted
Apparatus, System and Method for Facilitating Transfer of High Level Waste to and/or From a Spent Fuel Pool2016US 8,277,746 B2Granted
Ventilated Transfer Cask with a High Integrity Lifting Feature and an Integral Impact Limiter2016US 9,466,400 B2Granted
System and Method for the Ventilated Storage of High Level Radioactive Waste in a Clustered Arrangement2016US 9,460,821, US 8,660,230 B2Granted
A Multi-Cavity Canister Transfer Facility2016Provisional
Apparatus, System and Method for Storing High Level Waste2016US 9,269,464 B2, US 8,712,001 B2, US 8,548,112 B2Granted
System, Method and Apparatus for Providing Additional Radiation Shielding to High Level Radioactive Materials2015US 9,208,914 B2, US 8,995,604 B2Granted
Joining Process for Neutron Absorbing Materials2015US 2015/0336204 A1Published
Construction-Efficient Air Cooled Heat Exchanger in Outdoors Service2015Provisional
Method for Controlling Temperature of a Portion of a Radioactive Waste Storage System and for Implementing the Same2015US 9,105,365 B2Granted
Storage System for Nuclear Fuel2015US 2015/0221402 A1Published
Passive Reactor Containment Protection System2015US 9,786,393 B2Granted
Finned Tube Assemblies for Heat Exchangers2015US 2015/0027697 A1Published
Neutron Absorbing Fuel Insert Fabrication Techniques2014Provisional
Method of Transferring High Level Radioactive Materials, and System for the Same2014US 8,718,221 B2Granted
Heat Exchanger for Accommodating Thermal and/or Pressure Transients2013US 8,602,089 B2Granted
Apparatus and Method for Supporting Fuel Assemblies in an Underwater Environment Having Lateral Access Loading2012US 8,139,706 B2, US 7,715,517Granted
Method of Removing Radioactive Materials from Submerged State and/or Preparing Spent Nuclear Fuel for Dry Storage2011US 8,067,659 B2Granted
Method and Apparatus for Transporting and/or Storing Radioactive Materials having a Jacket Adapted to Facilitate Thermosiphon Fluid Flow2011US 7,994,380 B2Granted
Heat Exchanger Apparatus2010US 2010/0282451 A1Published
Apparatus for Providing Additional Radiation Shielding to a Container Holding Radioactive Materials, and Method of Using the Same to Handle and/or Process Radioactive Materials2010US 7,786,456 B2Granted
Method and Apparatus for Maximizing Radiation Shielding During Cask Transfer Procedures2008US 7,330,525 B2, US 6,587,536 B1Granted
Forced Gas Flow Canister Dehydration2007US 7,210,247 B2, US 7,096,600 B2Granted
Below Grade Cask Transfer Facility2006US 7,139,358 B2, US 6,793,450 B2Granted
System and Method for Transferring Spent Nuclear Fuel from a Spent Nuclear Fuel Pool to a Storage Cask2005US 6,853,697 B2, US 6,625,246 B1Granted
Seismic Cask Stabilization Device2005US 6,848,223 B2Granted
Ventilated Vertical Overpack2004US 6,718,000 B2Granted
Apparatus Suitable for Transporting and Storing Nuclear Fuel Rods and Methods for Using the Apparatus2000US 6,064,710, US 5,898,747Granted

Technical Papers

TitleAuthorYearEquipment Type
Analysis of Mechanical Impact Events in Spent Fuel Storage EquipmentChung, Bullard, Singh2020
Predicting the Response of the Impact Limiter in the HI-STAR Family of Transport Packages Using a Benchmarked LS-DYNA Dynamic ModelSingh, Zhai, Soler2007
On the Essential Characteristics of Underground Storage of Spent Nuclear Fuel in the HI-STORM 100 SystemSingh2007
Validation of an Impact Limiter Crush Prediction Model with Test Data: The Case of the HI-STAR 100 PackageSingh, Soler, Bullard2004
The Multi-Purpose Canister: A Bulwark of Safety in the Post-9/11 AgeSingh, Zhai2003
Predicting the Structural Response of Free-Standing Spent Fuel Storage Casks Under Seismic EventsSingh, Soler2001
Seismic Response Characteristics of HI-STAR 100 Cask System on Storage PadsSingh, Soler, Smith1998
A Structural Assessment of Candidate Fuel Basket Designs for Storage and Transport of Spent Nuclear FuelSingh, DeLong1998,
How the Pool Storage Industry Keeps its Head Well Above WaterSingh, Blessing1997
An Overview of the HI-STAR TechnologySingh1997
Application of Transient Analysis Methodology to Heat Exchanger Performance MonitoringRampall, Soler, Singh, Scott1994
Predicting Thermal Performance of Heat Exchangers Using In-Situ Testing and Statistical CorrelationSingh, Iulianetti, Scott1994
A Case for Wet StorageSingh1993
Some Results from Simultaneous Seismic Simulations of All Racks in a Fuel PoolSoler, Singh1993
Design Strength of Primary Structural Welds in Free-Standing StructuresSingh, Soler, Bhattacharya1991
A Rational Procedure for Analyzing Flanged and Flued Expansion JointsSingh, Soler1991
Transient Response of Large Inertia Cross Flow Heat ExchangersSingh, Wang, Iulianetti1991
Spent Fuel Storage Options: A Critical AppraisalSingh, Bale1990
An Elastic-Plastic Analysis of the Integral Tubesheet in U-Tube Heat Exchangers – Towards an ASME Code Oriented ApproachSoler, Singh1987
A Proposed Extension of the TEMA Tubesheet Design Method to Determine Tubesheet Rim ThicknessSingh, Marks1987
A Design Procedure for Evaluating the Tube Axial Load Due to Thermal Effects in Multi-Pass Fixed Tubesheet Heat ExchangersSingh, Soler1987
Tubesheet Analysis—A Proposed ASME Design ProcedureSoler, Caldwell, Singh1987
A Method for Computing Maximum Water Temperature in a Fuel Pool Containing Spent Nuclear FuelSingh, Soler, Gupta1986
Foundation Stresses under Support of Freestanding Equipment Subjected to External LoadsSingh, Gottesman, Soler1985
Operating Experience with Components in the Turbine cycleSingh, Menuchin, Hirota1985
Seismic Response of Free-Standing Fuel Rack Constructions to 3-D MotionsSoler, Singh1984
On Minimization of Rad-Waste Carryover in an n-Stage EvaporatorSingh, Holtz, Luk1984
Design Parameters Affecting Bolt Load in Ring Type Gasketed JointsSingh, Soler1983
Method for Quantifying Heat Duty Derating due to Inter-Pass Leakage in Bolted Flat Cover Heat ExchangersSingh1983
Effect of Nonuniform Inlet Air Flow on Air Cooled Heat Exchanger PerformanceSoler, Singh1983
Dynamic Coupling in a Closely Spaced Two-Body System Vibrating in Liquid Medium: The Case of Fuel RacksSoler, Singh1982
A Design Concept for Minimizing Tubesheet Stress and Tubejoint Load in Fixed Tubesheet Heat ExchangersSingh, Soler1982
An Approximate Method for Evaluating the Temperature Field in Tubesheet Ligaments of Tubular Heat Exchangers Under Steady-State ConditionsSingh1982
A Method for Maximizing Support Leg Stress in a Pressure Vessel Mounted on Four Legs Subject to Moment and Lateral LoadingsSingh1981
A Comparison of Thermal Performance of Two and Four Tube Pass Designs for Split Flow ShellsSingh1981
On the Necessary Criteria for Stream-Symmetric Tubular Heat Exchanger GeometriesSingh1981
Some Fundamental Relationships for Tubular Heat Exchanger Thermal PerformanceSingh1981
Optimization of Two Stage Evaporators for Minimizing Rad-Waste EntrainmentHoltz, Singh1980
An Approximate Analysis of Foundation Stresses in Horizontal Pressure VesselsSingh, Luk1980
Study of Bolted Joint Integrity and Inter-Tube-Pass Leakage in U-Tube Heat Exchangers: Part II – ApplicationSingh1979
Study of Bolted Joint Integrity and Inter-Tube-Pass Leakage in U-Tube Heat Exchangers: Part I – AnalysisSingh1979
On Thermal Expansion Induced Stresses in U-Bends of Shell-and-Tube Heat ExchangersSingh1979
Generalization of the Split Flow Heat Exchanger Geometry for Enhanced Heat TransferSingh, Holtz1979
Analysis of Temperature Induced Stresses in the Body Bolts of Single Pass Heat ExchangersSingh, Holtz1979
Heat Transfer Characteristics of a Generalized Divided Flow Heat ExchangerSingh1979
Analysis of Vertically mounted Through-Tube Heat ExchangersSingh1978
An Efficient Design Method for Obround Pressure Vessels and Their End ClosuresSingh1977
A Method to Design Shell-side Pressure Drop Constrained Tubular Heat ExchangersSingh1977
Contact Stresses for Multiply-Connected Regions – The Case of Pitted SpheresSingh, Paul, Woodward1976
Predicting Flow Induced Vibration in U-Bend Regions of Heat Exchangers – An Engineering SolutionSingh1976
Design of Skirt-Mounted SupportsSingh1976
Stress Concentration in Crowned RollersSingh, Paul1975
Application of Spiral Wound Gaskets for Leak Tight JointsSingh1975
On the Inadequacy of Hertzian Solution of Two-dimensional Line Contact ProblemsSingh1974
Numerical Solution of Non-Hertzian Elastic Contract ProblemsSingh, Paul1974
How to Locate Impingement Plates in Tubular Heat ExchangersSingh1974
A Method for Solving Ill-Posed Integral Equations of the First KindSingh, Paul1973

Videos