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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