Results 21 to 30 of about 19,519 (264)

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

Safety analysis of HWRR test fuel assembly in Tehran Research Reactor core using open loop test facility [PDF]

open access: yesمجله 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]

open access: yesمجله 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

A novel iterative learning control method and control system design for active magnetic bearing rotor imbalance of primary helium circulator in high-temperature gas-cooled reactor

open access: yesMeasurement + 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

open access: yesActa 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

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

The implication of Thorium fraction on neutronic parameters of pebble bed reactor

open access: yesKuwait 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

Control rods effect analyses on thermo-hydraulic safety parameters in TRR [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2020
In this study, the effect of control rods on TRR safety parameters was investigated in both cases of static and transient behavior. In this paper, the effect of the control rods movements (70%) on the power peaking was used in the form of the normalized ...
A. Lashkari   +2 more
doaj   +1 more source

Possibility of using real time digital neutron radiography to study the evaporation of water in porous materials [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2021
The study of the process of absorption and evaporation of fluids in porous media is of particular importance in sciences such as geology, civil engineering, environment, etc. Neutron radiography is one of the most precise methods for investigation of the
E. Nazemi   +4 more
doaj   +1 more source

CFD Analysis of Passive Autocatalytic Recombiner

open access: yesScience and Technology of Nuclear Installations, 2011
In water-cooled nuclear power reactors, significant quantities of hydrogen could be produced following a postulated loss-of-coolant accident (LOCA) along with nonavailability of emergency core cooling system (ECCS). Passive autocatalytic recombiners (PAR)
B. Gera   +3 more
doaj   +1 more source

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