4.5 Article

Numerical Simulation of Tritium Diffusion Behavior in FeCrAl Cladding

Related references

Note: Only part of the references are listed.
Article Nuclear Science & Technology

Assessment of BISON capabilities for component-level prediction of tritium transport in fusion and fission applications

Miles O'Neal et al.

Summary: In this study, the BISON fuel performance code was assessed for its application in hydrogen migration and redistribution modeling. The ability of the BISON models to predict tritium transport behavior in steel materials was demonstrated through reasonable agreement between reported values and BISON predictions. Sensitivity analysis revealed the most important parameter and the least important parameter for tritium migration in steels. Overall, the BISON code shows promising capabilities for component-level modeling of tritium transport.

FUSION ENGINEERING AND DESIGN (2022)

Review Materials Science, Multidisciplinary

Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review

Yogendra S. Garud et al.

Summary: The US Department of Energy is working on developing accident tolerant fuels (ATF) for light water reactors. Iron-chromium-aluminum (FeCrAl) alloys are being considered as a potential fuel cladding material. However, there is concern that using ferritic FeCrAl could result in an increase in tritium concentration in the coolant.

METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE (2022)

Article Chemistry, Physical

Synthesis of plasma-nitrided Cr coatings on HT9 steel for advanced chemical barrier property in a nuclear cladding application

Sunghwan Yeo et al.

Summary: Chromium-chromium nitride multi-coating barriers were synthesized on HT9 steel disks using the electroplating and RF plasma nitriding techniques to mitigate fuel-cladding chemical interactions. It was found that plasma nitriding could not only create an additional chromium nitride layer on the outer surface of the Cr coating, but also significantly improve the crack-closure effect on hard Cr coatings. Additionally, the 72-hour nitrided Cr coating showed excellent barrier properties without visible inter-diffusion when subjected to diffusion couple tests of Ce-Nd alloys at 650 degrees C for 25 hours.

APPLIED SURFACE SCIENCE (2022)

Article Materials Science, Multidisciplinary

High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments

Hwasung Yeom et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

Hydrogen permeation in FeCrAl alloys for LWR cladding application

Xunxiang Hu et al.

JOURNAL OF NUCLEAR MATERIALS (2015)

Article Materials Science, Multidisciplinary

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

K. A. Terrani et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments

B. A. Pint et al.

JOURNAL OF NUCLEAR MATERIALS (2013)

Article Nuclear Science & Technology

Study on the tritium behaviors in the VHTR system. Part 1. Development of tritium analysis code for VHTR and verification

Eung S. Kim et al.

NUCLEAR ENGINEERING AND DESIGN (2010)

Article Instruments & Instrumentation

Comprehensive review and critical evaluation of the half-life of tritium

LL Lucas et al.

JOURNAL OF RESEARCH OF THE NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY (2000)