© 2020 by the authors. Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (http://creativecommons.org/licenses/by/4.0/). The UK nuclear innovation programme supported by the government includes preparation for future ABWR construction. The UK has significant expertise in building and operating gas-cooled nuclear reactors and some experience with PWRs, while there is limited knowledge in BWR technologies. Hence, an important aim of this work is to understand the discrepancies between codes to assess uncertainties in BWR lattice and depletion calculations, while identifying specific development demands to progress existing too...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
Within the framework of the Horizon-2020 ESFR-SMART project, and with the objective of assessing and...
In order to improve the efficiency of dry used nuclear fuel (UNF) storage, reduced reactivity method...
The report describes the final results of the Phase IIIB Benchmark conducted by the Expert Group on ...
A thorium-fueled benchmark comparison was made in this study between state-of-the-art codes, WIMSD-5...
Since the use of deterministic transport code WIMS can significantly reduce the computational time c...
A depletion chain simplification method is applied to UNIST lattice code STREAM (Steady state and Tr...
RBMK fuel assemblies differ from other LWR FA due to a specific arrangement of the fuel rods, the lo...
Deterministic HELIOS-2.1 and SCALE-6.1 codes are compared using pin-cell models for light water reac...
Due to the challenges of spent fuel accumulation, the nuclear industry is exploring more cost-effect...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
A 1998 memo from the United States Nuclear Regulatory Commission, the Kopp Memo, proposed that for b...
As part of work to evaluate the potential benefits of using thorium in LWR fuel, a thorium fueled be...
The reactivity loss of PWR fuel with burnup has been investigated experimentally by measuring the re...
This paper aims to compare three Monte Carlo (MC) burnup based codes, i.e. MCNP6, Monteburns and Se...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
Within the framework of the Horizon-2020 ESFR-SMART project, and with the objective of assessing and...
In order to improve the efficiency of dry used nuclear fuel (UNF) storage, reduced reactivity method...
The report describes the final results of the Phase IIIB Benchmark conducted by the Expert Group on ...
A thorium-fueled benchmark comparison was made in this study between state-of-the-art codes, WIMSD-5...
Since the use of deterministic transport code WIMS can significantly reduce the computational time c...
A depletion chain simplification method is applied to UNIST lattice code STREAM (Steady state and Tr...
RBMK fuel assemblies differ from other LWR FA due to a specific arrangement of the fuel rods, the lo...
Deterministic HELIOS-2.1 and SCALE-6.1 codes are compared using pin-cell models for light water reac...
Due to the challenges of spent fuel accumulation, the nuclear industry is exploring more cost-effect...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
A 1998 memo from the United States Nuclear Regulatory Commission, the Kopp Memo, proposed that for b...
As part of work to evaluate the potential benefits of using thorium in LWR fuel, a thorium fueled be...
The reactivity loss of PWR fuel with burnup has been investigated experimentally by measuring the re...
This paper aims to compare three Monte Carlo (MC) burnup based codes, i.e. MCNP6, Monteburns and Se...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
Within the framework of the Horizon-2020 ESFR-SMART project, and with the objective of assessing and...
In order to improve the efficiency of dry used nuclear fuel (UNF) storage, reduced reactivity method...