Results 11 to 20 of about 173,657 (302)
Neutron Computerized Tomography (CT) of the non-irradiated fuel rod [PDF]
مجله علوم و فنون هستهای, 2020 Due to the special and difficult conditions for the fuel rods inside the reactor core, inspection and quality control of the fuel after the production at the factory and before loading in the core of the reactor is essential.
E. Nazemi +4 more
doaj +1 more source
Safety analysis of HWRR test fuel assembly in Tehran Research Reactor core using open loop test facility [PDF]
مجله علوم و فنون هستهای, 2021 HWRR element is an instrumented fuel assembly constructed based on JCPOA conceptual design parameters for Arak reactor. The in-core experiments of the fuel are carried out in TRR core to evaluate neutronic and thermal-hydraulic parameters using an ...
E. Abedi,, H. Khalafi, S.M. Mirvakili
doaj +1 more source
Burn up effect on optimal placement of fixed in-core detectors for Tehran research reactor using information theory [PDF]
مجله علوم و فنون هستهای, 2020 Monitoring the power distribution of reactor core is one of the most challenging issues in the safe operation of nuclear reactors. The Number and arrangement of detectors in a core monitoring system should be determined in a way that maximum amount of ...
M.S. Terman +2 more
doaj +1 more source
Measurement + Control, 2020 As one of the key technologies of high-temperature gas-cooled reactor, primary helium circulator–equipped active magnetic bearing provides driving force for primary helium cooling system. However, repetitive periodic vibration produced by rotor imbalance
Yangbo Zheng +4 more
doaj +1 more source
CFD simulation of partial channel blockage on plate-type fuel of TRIGA-2000 conversion reactor core
Acta Polytechnica, 2022 A nuclear reactor cooling system that has been operating for a long time can carry some debris into a fuel coolant channel, which can result in a blockage. An in-depth two-dimensional simulation of partial channel blockage can be carried out using FLUENT
Sukmanto Dibyo +4 more
doaj +1 more source
Urania, 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
Small reactor power systems for manned planetary surface bases [PDF]
, 1987 A preliminary feasibility study of the potential application of small nuclear reactor space power systems to manned planetary surface base missions was conducted. The purpose of the study was to identify and assess the technology, performance, and safety
Bloomfield, Harvey S.
core +2 more sources
Radiation safety based on the sky shine effect in reactor [PDF]
, 2020 In the reactor operation, neutrons and gamma rays are the most dominant radiation. As protection, lead and concrete shields are built around the reactor. However, the radiation can penetrate the water shielding inside the reactor pool.
Mahyuddin, Siti Nor Kalillah +2 more
core +1 more source
The Thorium Molten Salt Reactor : Moving on from the MSBR [PDF]
, 2005 A re-evaluation of the Molten Salt Breeder Reactor concept has revealed problems related to its safety and to the complexity of the reprocessing considered.
A. Nuttin +14 more
core +3 more sources
The implication of Thorium fraction on neutronic parameters of pebble bed reactor
Kuwait Journal of Science, 2021 Thorium abundance in the Earth's crust is estimated to be three to four times higher than uranium. This is one potential advantages of thorium as a provider of attractive fuel to produce nuclear energy.
Zuhair Zuhair +3 more
doaj +1 more source