A Technology Roadmap for Generation-IV Nuclear Energy Systems, USDOE/GIF-002-00

@inproceedings{Abram2002ATR,
  title={A Technology Roadmap for Generation-IV Nuclear Energy Systems, USDOE/GIF-002-00},
  author={Timothy J. Abram},
  year={2002}
}
  • T. Abram
  • Published 1 December 2002
  • Engineering
Digestion and trace metal analysis of uranium nitride
Uranium nitride is considered to be a possible fuel for fast reactors. Much of the research to date has targeted synthesis of uranium nitride. This work developed and optimized destructive assay
MODELLING ASTRID-LIKE SODIUM-COOLED FAST REACTOR WITH SERPENT-DYN3D CODE SEQUENCE
This study explores the feasibility of applying the Serpent-DYN3D sequence to the analysis of Sodium-cooled Fast Reactors (SFRs) with complex core geometries, such as the ASTRIDlike design. The core
Quantitative safety goals for fusion power plants: Rationales and suggestions
“How safe is safe enough?” is a key and fundamental question for any risky engineering and safety goals has been extensively studied in many fields, such as chemical industry, nuclear industry, etc.
Oxidation Behavior of an Austenitic Steel (Fe, Cr and Ni), the 310 H, in a Deaerated Supercritical Water Static System
The aim of this work was to study the corrosion behavior of a Fe-Cr-Ni alloy (310 H stainless steel) in water at a supercritical temperature of 550 °C and a pressure of 250 atm for up to 2160 h. At
Application of multiple linear regression to trip setpoint analysis in a reactivity‐initiated accident of a molten salt reactor
The trip setpoint parameters of a molten salt reactor have been analyzed by performing multiple linear regression (MLR) method. In the analysis, a reactivity‐initiated accident with inadvertent
...
...