Prospects for additive manufacturing of nuclear fuel forms
AT Nelson - Progress in Nuclear Energy, 2023 - Elsevier
Additive manufacturing (AM) is viewed as a critical enabling technology for achieving
superior performance and improved economics across many sectors. Although the past …
superior performance and improved economics across many sectors. Although the past …
BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms
BISON is a nuclear fuel performance application built using the Multiphysics Object-Oriented
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …
CAMPUS-ANNULAR: Preliminary multiphysics modeling of annular fuel performance under normal operating and accident conditions
The internal and external cooled annular fuel was proposed firstly by MIT, which is found to
be able to improve fuel performance dramatically. Based on the CAMPUS code, an annular …
be able to improve fuel performance dramatically. Based on the CAMPUS code, an annular …
The application of synchrotron micro-computed tomography to characterize the three-dimensional microstructure in irradiated nuclear fuel
This research demonstrated the first time that synchrotron X-ray micro-computed
tomography (μ-CT) was utilized to analyze the three-dimensional (3-D) morphology of the …
tomography (μ-CT) was utilized to analyze the three-dimensional (3-D) morphology of the …
Metallic fuel cladding degradation model development and evaluation for BISON
Fuel cladding chemical interaction (FCCI) and coolant cladding chemical interaction (CCCI),
both consume stainless-steel cladding in sodium-cooled fast reactors (SFRs), and effectively …
both consume stainless-steel cladding in sodium-cooled fast reactors (SFRs), and effectively …
Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor
This study investigates the neutronics characterization of the Allegro-75 MW th modular
reactor by analyzing three alternative heterogeneous core configurations-axial, radial, axial+ …
reactor by analyzing three alternative heterogeneous core configurations-axial, radial, axial+ …
Mitigating fuel cladding chemical interactions by enhancing chromium diffusion barrier performance using pulse reverse electroplating
S Yoo, S Yeo, JH Kim, HS Yun, JM Oh… - Journal of Nuclear …, 2024 - Elsevier
Fuel cladding chemical interaction (FCCI) is a critical issue affecting the safe usage of
metallic nuclear fuel in sodium-cooled fast reactors (SFRs). Although a chromium (Cr) …
metallic nuclear fuel in sodium-cooled fast reactors (SFRs). Although a chromium (Cr) …
Small-scale mechanical testing and characterization of fuel cladding chemical interaction between HT9 cladding and advanced U-based metallic fuel alloy
Fuel cladding chemical interaction (FCCI) occurred on the interface between the nuclear
metal fuel and cladding is the primary cause of cladding wastage, weakening cladding …
metal fuel and cladding is the primary cause of cladding wastage, weakening cladding …
Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)
A Ibrahim, M Aziz, SA El-Fiki, AA Galahom - Kerntechnik, 2022 - degruyter.com
The main objective of the presented work is to investigate the effectiveness of
homogenization of the GFR-2400 core in simulating its neutronic characteristics. To explore …
homogenization of the GFR-2400 core in simulating its neutronic characteristics. To explore …
The advanced characterization, post-irradiation examination, and materials informatics for the development of ultra high-burnup annular U-10Zr metallic fuel
U-Zr metallic fuel is a promising fuel candidate for Gen Ⅳ fast spectrum reactors. Previous
experimental irradiation campaigns showed that the sodium thermal bonded U-10Zr fuel …
experimental irradiation campaigns showed that the sodium thermal bonded U-10Zr fuel …