473 results
Showing 1–20 · 0.55 seconds · RSS
EPJ Nuclear Sciences & Technologies
Scopus
ISSN 2491-9292 · EDP Sciences · 473 articles in the index
-
Journal Article
Experimental uncertainty quantification using templates of expected measurement uncertainties for fast neutron-induced total, capture, and scattering cross sections
Careful experimental uncertainty quantification (UQ) is key for developing trustworthy evaluated nuclear data. Templates to account for missing or under-reported experimental uncertainties were recently developed by the covariance committee of Cross Section Evaluation Working Group (CSEWG). In this…
-
Journal Article
Compendium on Monte Carlo simulation of photoneutrons in the Giant Dipole Resonance energy range
Photoneutrons–neutrons produced through photonuclear reactions–play a critical role in radiation transport scenarios involving high-energy gamma sources, electron accelerators, and nuclear reactors. Accurate modeling of photoneutron production and transport is still a challenging problem, due to…
-
Journal Article
Robotic system for fragmentation of steam generators (StarGate)
The robotic complex “StarGate” was created in response to a request to design and deliver a device for the Nuclear Power Plant (NPP) V1 in Jaslovské Bohunice for the fragmentation of 12 steam generators. To meet the NPP’s requirements, a transdisciplinary team was assembled, consisting of experts…
-
Journal Article
Extension of the turbulent heat flux modelling in OpenFOAM for improved simulation of liquid metal flows
Turbulent heat transfer is a fundamentally complex physical process that has challenged turbulence modellers for many years. A full differential second-moment closure model provides a solid foundation for the derivation of the simpler Algebraic Heat Flux Model (AHFM), which retains the primary…
-
Journal Article
Reactive spark plasma sintering of UAlx + Al powder mixtures, prospects for manufacturing targets for 99Mo production
A U + 5 wt.% Al powder (written U-5Al), manufactured by centrifugal atomization, was used in this study to assess the feasibility of densifying UAlx + Al powder mixtures by Spark Plasma Sintering (SPS) and obtaining a final composition with a minimum content of UAl2 that meets specifications of…
-
Journal Article
Safety-related investigations designing a soluble-boron-free small modular reactor core at equilibrium
Many water-cooled SMRs (WC-SMRs) are being developed and their deployment is being considered in different countries world-wide, with some designs considering no soluble boron in the coolant. The elimination of soluble boron in the coolant of WC-SMRs offers advantages such as an enhanced negative…
-
Journal Article
Consistent quantification of energy uncertainties in experimental time-of-flight nuclear data across resolved, unresolved, and fast regimes
A major task for nuclear data evaluations is the curation of measurement data to be used in the inference of nuclear data quantities. The quality of the resulting measurement data uncertainty depends on the rigor of the evaluator reviewing the data set and the uncertainty information provided by…
-
Journal Article
Loading pattern design of the soluble boron-free SMR using LEU+ fuel and multitype burnable absorbers
Small Modular Reactors (SMRs) represent a promising technology for addressing global energy demands. South Korea’s innovative SMR (i-SMR) is targeting soluble boron-free (SBF) operation to simplify reactor systems and eliminate boric acid corrosion. However, the elimination of soluble boron…
-
Journal Article
Bias estimation for irradiated assembly reactivity decrement and burnup
In this paper, we are estimating biases for the reactivity decrement and burnup of irradiated fuel assemblies, based on differences between measured and calculated local in-core power measurements (flux maps). The simulations are performed with validated CASMO5 and SIMULATE5 cycle follow-up models…
-
Journal Article
Scarabée: A Free and Open-Source Lattice Physics Code
Scarabée is a new free and open source deterministic neutron transport toolkit. It is used as a Python library, giving access to a variety of 1D and 2D transport solvers, as well as 3D diffusion solvers. It also provides a PWR lattice physics calculation scheme, which automates the self-shielding…
-
Journal Article
A comparative study of production methods for nuclear-grade boron carbide powder
Two industrial-scale methods for synthesizing nuclear-grade boron carbide (B4C) powder have been investigated and compared: direct synthesis from elements and carbothermal reduction. A series of experiments using different boron (isotopically enriched 10B and 11B) and carbon sources (carbon black…
-
Journal Article
Exploring sustainability, societal perception, licensing and non-electric applications of new nuclear technologies: perspectives and achievements of ECOSENS, HARMONISE and SANE projects
Small Modular Reactors (SMRs) and Advanced Modular Reactors (AMRs) are seen today as promising solutions for enhancing Europe’s energy supply security and contributing to global climate change mitigation. Their successful deployment, however, is contingent upon robust political support, widespread…
-
Journal Article
The 0E2 benchmarks for PWR UO2 decay heat: an analysis from the NEA WPNCS
This paper presents the work performed in the subgroup 16 of the Working Party for Nuclear Criticality Safety (WPNCS) of the OECD Nuclear Energy Agency. The main goal was to define two decay heat benchmarks for Spent Nuclear Fuel (one pincell and one assembly), perform calculations and compare and…
-
Journal Article
High-precision measurement of 215Po half-life via delayed-coincidence analysis
We performed a high-precision study of the 215Po α-decay using a LaBr3 scintillating detector in a low-background environment. The 227Ac intrinsic contamination in the LaBr3 crystal undergoes a decay chain, producing the intermediate pair of 219Rn→215Po→211Pb decays. The fast time response and good…
-
Journal Article
Integration of minor actinide coatings into (Th, 233U)O2 fuel: A strategy for excess reactivity mitigation and radioactivity management
This study investigates the application of minor actinides (MAs) as a cladding layer on thorium–uranium fuel to simultaneously mitigate excess reactivity at the beginning of the fuel cycle (BOC) and provide an effective pathway for MA transmutation. Four different MA loadings, represented by…
-
Journal Article
Impact of silicon on neutronic performance and microstructural evolution of FeCrAl alloys for ATF cladding
FeCrAl alloys are promising candidate for accident tolerant fuel (ATF) cladding in light water-cooled nuclear reactors (LWRs) due to their excellent high-temperature oxidation resistance and mechanical strength. This study investigates the effect of silicon (Si) additions (0–8.00 wt.%) on the…
-
Journal Article
Bias and uncertainty estimates for in-core LWR reaction rate distributions
We analyze in-core reaction rate measurements coming from three Pressurized Water Reactors and two Boiling Water Reactors (named E) and compare them with CASMO5 and SIMULATE-3 (and -5) calculations (named C). A total of almost 1 million experimental values were considered, covering various cycles…
-
Journal Article
Numerical assessment of spacer grid geometry on turbulence anisotropy in a rod bundle
The highly turbulent flow circulating between the rods inside a Pressurised Water Reactor (PWR) core creates turbulence induced vibrations. To get a better understanding of the flow characteristics, the French Alternative and Atomic Energy Commission (CEA) had built and operated CALIFS 5x5-test…
-
Journal Article
Micro-scale characterization of brittle fracture in UO2 nuclear fuel: finite element methodology for 2D and 3D simulation
This work is conducted within the framework of nuclear fuel safety analyses involving multiscale modelling of UO2 fuel pellet fragmentation process. In this paper, a Finite Element (FE) methodology is proposed in order to enable 2D and 3D simulation of brittle fracture in micro-scale specimens used…