Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward

An integrated model of tritium transport and corrosion in Fluoride Salt-Cooled High-Temperature Reactors (FHRs) – Part I: Theory and benchmarking

(2016) John D. Stempien et al.   NUCLEAR ENGINEERING AND DESIGN

Basis for Fluoride Salt–Cooled High-Temperature Reactors with Nuclear Air-Brayton Combined Cycles and Firebrick Resistance-Heated Energy Storage

(2016) Charles Forsberg et al.   NUCLEAR TECHNOLOGY

Liquid Fuel Molten Salt Reactors for Thorium Utilization

(2016) Jess C. Gehin et al.   NUCLEAR TECHNOLOGY

Survey of advanced nuclear technologies for potential applications of sonoprocessing

(2016) Floren Rubio et al.   ULTRASONICS

ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets

(2015) B.N. Sorbom et al.   FUSION ENGINEERING AND DESIGN

Trapping State of Hydrogen Isotopes in Carbon and Graphite Investigated by Thermal Desorption Spectrometry

(2015) H. Atsumi et al.   FUSION SCIENCE AND TECHNOLOGY

Study on the Air Core Formation of a Gas–Liquid Separator

(2015) Junlian Yin et al.   JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME

Thermal hydraulics analysis of the Advanced High Temperature Reactor

(2015) Dean Wang et al.   NUCLEAR ENGINEERING AND DESIGN

Spent Nuclear Fuel and Graphite Management for Salt-Cooled Reactors: Storage, Safeguards, and Repository Disposal

(2015) Charles Forsberg et al.   NUCLEAR TECHNOLOGY

Advanced Nuclear Open Air-Brayton Cycles for Highly Efficient Power Conversion

(2015) Bahman Zohuri et al.   NUCLEAR TECHNOLOGY

Investigation of morphology and hydrogen adsorption capacity of disordered carbons

(2014) Lilin He et al.   CARBON

Reheat Air-Brayton Combined Cycle Power Conversion Off-Nominal and Transient Performance

(2014) Charalampos Andreades et al.   JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME

Reheat-Air Brayton Combined Cycle Power Conversion Design and Performance Under Nominal Ambient Conditions

(2014) Charalampos Andreades et al.   JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME

The molten salt reactor (MSR) in generation IV: Overview and perspectives

(2014) Jérôme Serp et al.   PROGRESS IN NUCLEAR ENERGY

Molten salts database for energy applications

(2013) R. Serrano-López et al.   CHEMICAL ENGINEERING AND PROCESSING

Sealing nuclear graphite with pyrolytic carbon

(2013) Shanglei Feng et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal desorption of hydrogen from carbon and graphite at elevated temperatures

(2013) H. Atsumi et al.   JOURNAL OF NUCLEAR MATERIALS

In situ measurement of tritium permeation through stainless steel

(2013) Walter G. Luscher et al.   JOURNAL OF NUCLEAR MATERIALS

Desorption of hydrogen trapped in carbon and graphite

(2013) H. Atsumi et al.   JOURNAL OF NUCLEAR MATERIALS

Protection of nuclear graphite toward liquid fluoride salt by isotropic pyrolytic carbon coating

(2013) Xiujie He et al.   JOURNAL OF NUCLEAR MATERIALS

Unique hydrogen adsorption properties of graphene

(2010) Lifeng Wang et al.   AICHE JOURNAL

Kinetic effect of Pd additions on the hydrogen uptake of chemically-activated ultramicroporous carbon

(2010) Vinay V. Bhat et al.   CARBON

Hydrogen behavior in carbon and graphite before and after neutron irradiation – Trapping, diffusion and the simulation of bulk retention–

(2010) H. Atsumi et al.   JOURNAL OF NUCLEAR MATERIALS

Atypical hydrogen uptake on chemically-activated, ultramicroporous carbon

(2009) Vinay V. Bhat et al.   CARBON

Bulk hydrogen retention in neutron-irradiated graphite at elevated temperatures

(2009) H. Atsumi et al.   JOURNAL OF NUCLEAR MATERIALS

Practical aspects for characterizing air oxidation of graphite

(2008) Cristian I. Contescu et al.   JOURNAL OF NUCLEAR MATERIALS

A novel approach to fabricating fuel compacts for the next generation nuclear plant (NGNP)

(2008) P.J. Pappano et al.   JOURNAL OF NUCLEAR MATERIALS

Hydrogen trapping in neutron-irradiated graphite

(2008) H. Atsumi et al.   JOURNAL OF NUCLEAR MATERIALS