Scott Willms Publications

• A Continuous Cryogenic Diffusion Pump For Fusion Reactors-Foster (2006)
  
• A credible pathway for heavy ion driven target fabrication and injection-Goodin (2002)
  
• A New Solid State Tritium Surface Monitor - Willms (2005)
  
• A Potential Capability for Initial Testing of Fusion Materials based on the LANL Low Energy Demonstration Accelerator (LEDA) Facility-Post (2004)
  
• Adsorption Isotherms for Tritium on Various Adsorbents at Liquid Nitrogen temperature-Kawamura (2000)
  
• Alternative analysis for fuel storage and delivery in the ITERTritium Plant-Chang (2014)
  
• An Overview of the US DCLL ITER TBM Program-Wong (2009)
  
• An overview of the US DCLL ITER-TBM program-Wong (2010)
  
• An overview of US ITER test blanket module program-Ying (2006)
  
• Analysis of High-Pressure, Multiphase Batch Reactor Data-Willms (1985)
  
• APD imaging probe for tritium surface contamination-Myers (2008)
  
• Aqueous Phase Oxidation-The Effect of Soil on Oxidation Kinetics-Willms (1988)
  
• Aqueous Phase Oxidation-The Intrinsic Kinetics of Single Organic Compounds-Willms (1987)
  
• Aqueous-Phase Oxidation - Rate Enhancement Studies-WILLMS (1987)
  
• Behavior of tritium in the TSTA test cell combined with operation of the Experimental Tritium Cleanup (ETC) system-WILLMS (2002)
  
• Comparison of methods for separating small quantities of hydrogen isotopes from an inert gas-Willms (1997)
  
• Cryogenic adsorption of low-concentration hydrogen on charcoal- 5A molecular sieve-UOP S-115- ZSM-5 and Wessalith DAY-Willms (1993)
  
• Decontamination studies of JAERI FCU and glovebox installed at the TSTA-Bartlein (1995)
  
• Demonstration of Regulatory Process Controls on the TSTA Cryogenic Distillation System-Willms (1995)
  
• Design of an Impurities Detritiation System for ITER using a Palladium Membrane Reactor-Birdsell _1998_
  
• Development Of Innovative Fuelling Systems For Fusion Energy Science - Gouge (1996)
  
• Dynamic Simulation of a Proposed ITER Tritium Processing System-Kuan (1995)
  
• Effect of inlet conditions on the performance of a palladium membrane reactor-Birdsell (1997)
  
• Experience of TSTA Milestone Runs with 100 grams-level of Tritium-Willms (1988)
  
• Extended operation of reactor-scale fusion fuel loop under US-Japan collaboration-Konishi (1993)
  
• Findings of the US research needs workshop on the topic of fusion power-Meier (2010)
  
• Fuel Cleanup Systems for Fusion Fuel Processing-Willms (1991)
  
• Fusion fuel purification during the Tritium Systems Test Assembly 3-week loop experiment-Wllims (1989)
  
• Fusion materials science and technology research opportunities now and during the ITER era-Zinkle (2014)
  
• Fusion tritium research facilities in KAERI-Chung (2012)
  
• Helium-cooled refractory alloys first wall and blanket evaluation-Wong (2000)
  
• Initial testing of a low pressure permeator for tritium processing-Willms (2000)
  
• ITER R&D Auxiliary systems Tritium systems-Yoshida (2001)
  
• Mathematical Comparison of Three tritium System Effluent HTO Cleanup Systems-Willms (2002)
  
• Method for Simultaneous Recovery of Hydrogen from Water and from Hydrocarbons-Willms (1996)
  
• Modeling and Data Analysis of a Palladium membrane Reactor for Tritiated impuriteis Cleanup-Birdsell (1995)
  
• Nuclear Modules of ITER TOKAMAK Sytems Code-Gohar (1988)
  
• Numerical Estimation Method of the Hydogen Isotope Inventory in the Hydrogen Isotope Separation System for Fusion Reactor-Iwai (2002)
  
• Operation Of A Simulated Non-Steady Tokamak Fuel Loop Using The Tritium Systems Test Assembly-Konishi (1995)
  
• Operation of a simulated non-steady tokamak fuel loop using the tritium systems test assembly-Willms (1995)
  
• Operation of a Simulated Nonsteady TOKAMAK Fuel Loop Using The Tryitium Systems Test Assembly-KONISHI (1995)
  
• Overview of fusion nuclear technology in the US-Morley (2006)
  
• Overview of the LIFE fuel cycle-Reyes (2013)
  
• Overview of the US ITER Dual Coolant Lead Lithium (DCLL) Test Blanket Module Program-Wong (2006)
  
• Peformance of a Palladium Membrane Reactor Using an Ni Calyst for Fusion Fuel Impurities Processing-WILLMS (1995)
  
• Pellet Injector Development at ORNL-Willms (1997)
  
• Practical-Scale Tests of Cryogenic Molecular-Sieve for Separating Low-Concentration Hydrogen Isotopes From Helium-Willms (1995)
  
• Progress and challenges of the ITER TBM Program from the IOperspective - Giancarli - 2016
  
• Progress On DCLL Blanket Concept-Wong (2013)
  
• Pure hydrogen production from octane, ethanol, methanol and methane reforming using a palladium membrane reactor-Birdsell (1997)
  
• Recent Palladium membrane Reactor Development at The Tritium Systems Test Assembly-Willms (1995)
  
• Recovery of hydrogen from impurities using a palladium membrane reactor-Willms (1993)
  
• Review of the ITER Fuel Cycle-Babineau (2010)
  
• Risk Reduction Using Innovative Tritium D&D TEchnologies at Los Alamos National Laboratory-Langsted-2004
  
• Risk Reduction Using Innovative Tritium D&D TEchnologies at Los Alamos National Laboratory-Langsted-2004
  
• Risk-based multi-criteria design concept of the ITER SDS getter bed-Yun (2014)
  
• Separation of helium and hydrogen isotopes by ISS at the TSTA-Enoeda (1989)
  
• Simplified Analysis of a Plug-Flow Palladium Permeator-Willms (1992)
  
• Simplified Estimation of Tritium Inventory in Stainless Steel - Willms (2005)
  
• Solid breeder test blanket module design and analysis-Ying (2005)
  
• Steady-State Computer Modeling of a Recent H-D-T Cryogenic Distillation experiment at TSTA-Young (2002)
  
• Study on Sudden Loss of Cryogenic Coolant Accident Happened in the Hydrogen Isotope Separation System for Fusion Reactor-Iwai (2002)
  
• Surface Characterization of TFTR First Wall Graphite Tiles Used During DT Operations-Paffett (2002)
  
• Testing of a practical low pressure permeator-Howard (1999)
  
• Thermal Response of Tritiated Codeposits from JET and TFTR to Transient Heat Pulses-Skinner (2003)
  
• Time-Dependant Tritium Inventories and Flow-Rates in Fuel-Cycle Components of a TOKAMAK Fusion Reactor-KUAN (1995)
  
• Tritium Behavior Intentionally Released in Radiological Controlled Room Under The US-Japan Collaboration at TSTA_LANL-Hayashi (1998)
  
• Tritium Behavior Intentionally Released in the Room-Kobayashi (2008)
  
• Tritium conductivity and isotope effect in proton-conducting perovskites-Mukundan (1999)
  
• Tritium loss in Molten Flibe Systems-Longhurst (2000)
  
• Tritium Module for ITER_TIBER System Code-Finn
  
• Tritium permeation experiment using a tungsten armored divertor-simulating module-Nakamura (200)
  
• Tritium Recovery and Isotope Separation Using Electrochemical Methods-Garzon (00)
  
• Tritium recovery from tritiated water with a two-stage palladium membrane reactor-Birdsell (1998)
  
• Tritium retention behavior in tungsten exposed to off-normal plasma condition-Nakamura (1999)
  
• Tritium retention study of tungsten using various hydrogen isotope irradiation sources-Ohira (1998)
  
• Tritium Retention Study of Tungsten using Various hydrogen isotope irradiation sources-Willms (1998)
  
• Tritium Systems Test Assembly (TSTA) Stabilization - Tesch (2005)
  
• TSTA Loop Operation with 100 Grams-Level f Tritium_Full Components Milestone Run in June1988-Willms (1988)
  
• TSTA Loop Operation with 100 Grams-level of Tritium_Milestone Run in July 1987-Willms (1988)
  
• TSTA Loop Operation with 100 Grams-Level of Tritum_ Milestone Run in June1987-Willms (1988)
  
• U.S. TRITIUM PLANT ACTIVITIES FOR ITER-Willms (2005)
  
• Ultra-High Tritium Decontamination Of Simulated Fusion Fuel Exhaust Using A 2-Stage Palladium Membrane Reactor-Birdsell (1996)
  
• US Tritium Activities-Willms (2002)
  
• Use of Magnesium for Recovering Hydrogen Isotopes from Tritiated Water-Willms-1994