Results 11 to 20 of about 3,602,304 (354)
Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project [PDF]
, 2015 Since some years, there is a worldwide trend to move towards “higher-fidelity” simulation techniques in reactor analysis. One of the main objectives of the research in this area is to enhance the prediction capability of the computations used for safety ...
B. Chanaron +7 more
semanticscholar +2 more sources
Nuclear 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]
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
Deterministic Safety Technology for RBMK Reactors [PDF]
Science and Technology of Nuclear Installations, 2008 The present paper deals with the description of the technical activities conducted within the TACIS Project R2.03/97, 2 EC Contract no. 30303, related to RBMK. The project activities are focused toward the setting-up of a chain of computational tools suitable for the analysis of transients expected in the RBMK nuclear power plant (NPP).
D'AURIA, FRANCESCO SAVERIO +3 more
openaire +5 more sources
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
The development of the reactor safety film [PDF]
Proceedings of the May 4-7, 1981, national computer conference on - AFIPS '81, 1981 The first computer-generated film of LASL's Reactor Safety efforts was developed using the ANIMATE framework, a program that adds visual capabilities to MAPPER. Numerous software limitations had to be overcome within a very limited production schedule.
Nancy N. Sheheen, Patrick J. Hodson
openaire +1 more source
Evaluation of an intensified continuous heat-exchanger reactor for inherently safer characteristics [PDF]
, 2008 The present paper deals with the establishment of a new methodology in order to evaluate the inherently safer characteristics of a continuous intensified reactor in the case of an exothermic reaction.
Elgue, Sébastien +5 more
core +1 more source