Analysis of fabrication and crack-induced porosity migration in mixed oxide fuels for sodium fast reactors by the finite element method

Development of fuel performance analysis code, BISON for MOX, named Okami: Analyses of pore migration behavior to affect the MA-bearing MOX fuel restructuring

(2021) Takayuki Ozawa et al.   JOURNAL OF NUCLEAR MATERIALS

Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment

(2021) L. Luzzi et al.   Nuclear Engineering and Technology

MFEM: A modular finite element methods library

(2020) Robert Anderson et al.   COMPUTERS & MATHEMATICS WITH APPLICATIONS

Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications

(2020) A. Magni et al.   JOURNAL OF NUCLEAR MATERIALS

Enhancing FRAPCON fuel performance code for physical phenomena at high temperature and high burnup

(2019) Yanin Sukjai et al.   JOURNAL OF NUCLEAR MATERIALS

Multi-physics modelling of the pellet-to-cladding gap closure phenomenon for SFR fuel performance codes

(2019) M. Temmar et al.   JOURNAL OF NUCLEAR MATERIALS

Modeling porosity migration in LWR and fast reactor MOX fuel using the finite element method

(2018) Stephen Novascone et al.   JOURNAL OF NUCLEAR MATERIALS

GERMINAL, a fuel performance code of the PLEIADES platform to simulate the in-pile behaviour of mixed oxide fuel pins for sodium-cooled fast reactors

(2018) Marc Lainet et al.   JOURNAL OF NUCLEAR MATERIALS

Development of a mixed oxide fuel pin performance analysis code “CEDAR”: Models and analyses of fuel pin irradiation behavior

(2014) Tomoyuki Uwaba et al.   NUCLEAR ENGINEERING AND DESIGN

Restructuring and redistribution of actinides in Am-MOX fuel during the first 24h of irradiation

(2013) Kosuke Tanaka et al.   JOURNAL OF NUCLEAR MATERIALS

Modelling actinide redistribution in mixed oxide fuel for sodium fast reactors

(2013) Valentino Di Marcello et al.   PROGRESS IN NUCLEAR ENERGY

Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels

(2012) Masato KATO et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

MACROS benchmark calculations and analysis of fission gas release in MOX with high content of plutonium

(2012) Sergei E. Lemehov et al.   PROGRESS IN NUCLEAR ENERGY

Modeling of thermo-mechanical and irradiation behavior of mixed oxide fuel for sodium fast reactors

(2009) Aydın Karahan et al.   JOURNAL OF NUCLEAR MATERIALS