Results 11 to 20 of about 23,738 (260)

Thermal hydraulic analysis of a tubular fuel assembly in the normal operating condition of Tehran Research Reactor core [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2022
The purpose of this paper is to investigate the possibility of using tubular fuel assemblies in Tehran Research Reactor (TRR) from the thermal hydraulic perspective.
M. Hasanzadeh   +4 more
doaj   +1 more source

Study on kinetic parameters characteristics of pebble bed reactor using HTR-proteus facility [PDF]

open access: yesNuclear Technology and Radiation Protection, 2022
The inherent safety feature of a pebble-bed reactor can be observed from its kinetic parameters. Proper modeling for calculating the reactor kinetic is also a concern for safe operation during normal and transient conditions.
Zuhair   +4 more
doaj   +1 more source

Rapid evaluation of particle properties using inverse SEM simulations

open access: yesEPJ Web of Conferences, 2017
The characteristic X-rays produced by the interactions of the electron beam with the sample in a scanning electron microscope (SEM) are usually captured with a variable-energy detector, a process termed energy dispersive spectrometry (EDS).
Bekar Kursat B.   +3 more
doaj   +1 more source

Small Modular Nuclear Reactors

open access: yes, 2020
Small modular reactors (SMRs) encompass a large number of technologies at different stages of development. A key challenge for SMR stakeholders is the evaluation of SMR competitiveness with respect to large reactors (LRs). SMRs are usually considered less competitive than LRs because of a misguided application of the economy of scale principle. However,
Locatelli, G, Mignacca, B
openaire   +3 more sources

CONCEPTUAL FUEL ELEMENT DESIGN CANDIDATES FOR CONVERSION OF HIGH FLUX ISOTOPE REACTOR WITH LOW-ENRICHED URANIUM SILICIDE DISPERSION FUEL* [PDF]

open access: yesEPJ Web of Conferences, 2021
Engineering design studies are underway to assess the feasibility of converting the High Flux Isotope Reactor (HFIR) to operate with low-enriched uranium silicide dispersion (LEU3Si2-Al) fuel. These studies are supported by the U.S.
Chandler D.   +4 more
doaj   +1 more source

Design, construction, and characterization of a Prompt Gamma Neutron Activation Analysis (PGNAA) system at Isfahan MNSR

open access: yesNuclear Engineering and Technology, 2023
In this research, a prompt gamma neutron activation analysis (PGNAA) system is designed and constructed based on the use of a low power research reactor.
M.H. Choopan Dastjerdi   +2 more
doaj   +1 more source

An Interpretable Dynamic Feature Search Methodology for Accelerating Computational Process of Control Rod Descent in Nuclear Reactors

open access: yesEnergies
Within the operational dynamics of a nuclear reactor, the customary approach involves modulating the reactor’s power output by means of control rod manipulation, which effectively alters the neutron density across the core.
Qingyu Huang   +8 more
doaj   +1 more source

Multi-objective optimization design of steam generators based on a novel dual population genetic algorithm

open access: yesNuclear Engineering and Technology
Aiming at the limitations of poor convergence and low optimization accuracy of genetic algorithm, a novel dual-population genetic algorithm (DPGA) is proposed and used to optimize the weight and volume of a vertical U-tube natural circulation steam ...
Yifu Han   +5 more
doaj   +1 more source

Mechanochemical Synthesis and Characterization of Nanostructured ErB4 and NdB4 Rare‐Earth Tetraborides

open access: yesAdvanced Engineering Materials, Volume 27, Issue 6, March 2025.
ErB4 and NdB4 nanostructured powders are produced by mechanochemical synthesis. 5 h mechanical alloying and 4 M HCl acid leaching are used in the production. ErB4 and NdB4 powders exhibit maximum magnetization of 0.4726 emu g−1 accompanied with an antiferromagnetic‐to‐paramagnetic phase transition at about TN = 18 K and 0.132 emu g−1 with a maximum at ...
Burçak Boztemur   +5 more
wiley   +1 more source

VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK

open access: yesUrania, 2021
VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK. Determination of neutronic parameter value is an important part in determining reactor safety, so accurate calculation results can be obtained.
Wahid Luthfi, Surian Pinem
doaj   +1 more source

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