An integrated statistical-thermodynamic model for fission gas release and swelling in nuclear fuels

CKC Lieou, NA Capps, MWD Cooper… - Journal of Nuclear …, 2024 - Elsevier
We propose a new model for burst fission gas release induced by microcracking in ceramic
nuclear fuels such as uranium dioxide. The model stipulates that the densities of defects in …

Kinetics of Recrystallization and Fission-Gas-Induced Swelling in High Burnup UO2 and U3Si2 Nuclear Fuels

J Rest, GL Hofman - Fundamental Aspects of Inert Gases in Solids, 1991 - Springer
Recent observations on experimental low-temperature swelling of irradiated uranium
suicide dispersion fuels have indicated that the growth of fission-gas bubbles appears to be …

Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients

T Barani, G Pastore, A Magni, D Pizzocri… - Journal of Nuclear …, 2020 - Elsevier
The description of intra-granular fission gas behavior during irradiation is a fundamental part
of models used for the calculation of fission gas release and gaseous swelling in nuclear …

Dynamics of irradiation-induced grain subdivision and swelling in U3Si2 and UO2 fuels

J Rest, GL Hofman - Journal of Nuclear materials, 1994 - Elsevier
Observations on low-temperature swelling of irradiated uranium silicide dispersion fuels
have shown that the growth of fission-gas bubbles is strongly affected by fission rate. The …

Effect of non-equilibrium fission gas and fuel creep on swelling and release in irradiated carbide fuels

AR Wazzan, J Tatsumi, D Okrent, MC Billone - Nuclear Engineering and …, 1985 - Elsevier
The code UCSWELL was developed to simulate fission gas behavior in carbide fuels. In the
present work, one of the limiting assumptions in UCSWELL-that matrix gas bubbles are in …

The response of fission gas bubbles to the dynamic behavior of point defects

JM Griesmeyer, NM Ghoniem - Journal of Nuclear Materials, 1979 - Elsevier
A model has been developed to investigate the response of fission gas bubbles to the
dynamic behavior of uranium point defects in uranium oxide. Simple thermodynamics is …

A kinetic rate theory modelling of fission gas release and fuel swelling for UN fuels

Z Qian, W Liu, R Yu, Y Tao, D Yun, L Gu - Journal of Nuclear Materials, 2021 - Elsevier
Fission gas behavior and fuel swelling have always been an important issue for nitride fuels.
In this paper, a mechanistic fission gas behavior model of nitride fuels has been established …

A dynamic intragranular fission gas behavior model

JM Griesmeyer, NM Ghoniem, D Okrent - Nuclear Engineering and Design, 1979 - Elsevier
A model for the non-equilibrium behavior of intragranular fission gas in uranium oxide fuel is
developed to study the fundamental phenomena that determine fission gas effects. The …

Modeling fragmentation and spallation of oxide reactor fuel during transient heating including the effects of burnup and fission product distribution

RJ DiMelfi, JM Kramer - Nuclear Technology, 1983 - Taylor & Francis
Characteristics of solid fuel fragmentation and energetic spallation during hypothetical
accident transients are calculated. Fission gas, having migrated to the grain boundaries as …

Analysis of fission gas release and gaseous swelling in UO2 fuel under the effect of external restraint

YH Koo, BH Lee, DS Sohn - Journal of nuclear materials, 2000 - Elsevier
To analyze fission gas release and gaseous swelling in UO2 fuel, a model has been
developed that can be used under both steady-state and transient operating conditions up to …