Feasibility study of fuel cladding performance for application in ultra-long cycle fast reactor

JA Jung, SH Kim, SH Shin, IC Bang, JH Kim - Journal of nuclear materials, 2013 - Elsevier
As a part of the research and development activities for long-life core sodium-cooled fast
reactors, the cladding performance of the ultra-long cycle fast reactor (UCFR) is evaluated …

Electronic origin of void formation in fcc metals

X Zhang, G Lu - Physical Review B—Condensed Matter and Materials …, 2008 - APS
Voids can be formed by supersaturation of vacancies created by energetic particle
irradiation, quenching, or mechanical deformation. By using multiscale simulations, we …

An approach for evaluating the integrity of fuel applied in Innovative Nuclear Energy Systems

N Nakae, T Ozawa, H Ohta, T Ogata… - Journal of Nuclear …, 2014 - Elsevier
One of the important issues in the study of Innovative Nuclear Energy Systems is evaluating
the integrity of fuel applied in Innovative Nuclear Energy Systems. An approach for …

Coupled quantum mechanics/molecular mechanics modeling of metallic materials: Theory and applications

X Zhang, G Lu - Journal of Materials Research, 2018 - cambridge.org
We review two recent advances in coupled quantum mechanics/molecular mechanics
(QM/MM) modeling for metallic materials. The QM/MM methods are formulated based on …

[图书][B] Das Bestrahlungsverhalten des austenitischen Stahls DIN 1.4970

R Hübner - 2000 - digbib.bibliothek.kit.edu
Zusammenfassung Das Bestrahlungsverhalten des austenitischen Stahls DIN 1.4970 (15%
Cr, 15% Ni, 1, 6% Mn, 1, 5% Mo, 0, 4–1% Si, 0, 3–0, 5% Ti) wurde im …

An approach for evaluating fuel system applied in innovative nuclear energy system

N Nakae, T Ozawa, H Ohta, T Ogata… - Progress in Nuclear …, 2011 - Elsevier
One of the important issues in the study of Innovative Nuclear Energy Systems (INES) is the
integrity of the fuel system applied. An approach of evaluating fuel system integrity is …

[图书][B] Untersuchungen zur Sättigung des Volumenschwellens im austenitischen Stahl DIN 1.4864 während der Bestrahlung mit Neutronen

R Hübner - 1999 - digbib.bibliothek.kit.edu
Zusammenfassung Im Bestrahlungsexperiment PFR-M2 wurden Druckkapseln aus dem
Werkstoff DIN 1.4864 (0, 07% C, 15% Cr, 35% Ni, 1, 6% Si, 1, 2% Mn) bei nominell 420 und …