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Validation of PWR Neutronics Code Package TORCH V2.0 With Nuclear Power Plant Measurements
Frontiers in Energy Research, 2022 This article presents the verification and validation (V and V) of PWR neutronics code package TORCH V2.0 with nuclear power plant (NPP) measurements. The advanced nuclear power engineering design software, TORCH V2.0, was developed by the Nuclear Power ...
Bin Zhang +4 more
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Confirmation of Nuclear Heating Rate for Installation of Cold Neutron Source at HANARO [PDF]
EPJ Web of Conferences, 2020 In order to determine the capacity of the cold neutron source refrigerator of HANARO, the nuclear heating rate at CN vertical hole is measured by using the heat-flow calorimetric method and confirmed by the calculation.
Myong-Seop Kim, Byung-Gun Park
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Development the nuclear decay data sublibrary for fission product [PDF]
EPJ Web of Conferences, 2020 Accurate and reliable nuclear decay data libraries are essential for calculation and design of the advanced nuclear systems. To meet the requirements of decay heat calculation, burn-up calculation, analysis neutrino spectra anomaly and the other related ...
Xiaolong Huang +3 more
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Frontiers in Energy Research, 2018 Nuclear electric propulsion (NEP) offers unique advantages for the interplanetary exploration. The extremely high conversion efficiency of magnetohydrodynamics (MHD) conversion nuclear reactor makes it a highly potential space power source in the future,
Jian Song +3 more
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Thermal-hydraulically calculation for the Dalat nuclear research reactor
Vietnam Journal of Mechanics, 1991 This paper concerns with thermal-hydraulically calculation for the core domain of the Dalat nuclear reactor in the nominal regime of works. On the base of this calculation some conclusions. On thermal safely of the reactor are conducted.
Ngo Phu Khang
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Simulation of Steady States of Helium Loop at Long Time Scenarios [PDF]
MATEC Web of Conferences, 2020 The natural circulation helium loop is an experimental facility designed for the research of the possibility of utilizing natural convection cooling for the case of decay heat removal from a fast nuclear reactor.
Világi František +6 more
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BETA EFFECTIVE SENSITIVITY TO NUCLEAR DATA WITHIN THE APOLLO3® NEUTRONIC PLATFORM [PDF]
EPJ Web of Conferences, 2021 In this paper, we present a sensitivity analysis of the beta effective to nuclear data for the UM17x17 experiment that has been performed in the EOLE reactor. This work is carried out using the APOLLO3® platform.
Valocchi G., Archier P., Tommasi J.
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Transient analysis on the thermal-mechanical characteristics of a heat pipe cooled reactor core
He jishu, 2022 BackgroundAs a nuclear power system with high energy density and strong adaptability, heat pipe cooled reactor can play an important role in space and deep sea exploration, and is attracting more and more attention from all over the world.
LIU Bo +4 more
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Atom Indonesia, 2021 Diffusion approximation is an important approximation used to model a nuclear reactor core with a quite good accuracy and less computational cost. This approximation has been used widely around the globe for various kinds of nuclear reactors.
H. Ardiansyah, M. R. Oktavian
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Computer Simulator for the Research Reactor IPEN/MB-01
Brazilian Journal of Radiation Sciences, 2020 A computer simulator for the Nuclear Research Reactor IPEN / MB-01 was developed to be a tool for teaching, training and recycling professionals. The simulator was developed on a SCADA platform (Supervision and Data Acquisition System) with support ...
Marcelo da Silva Rocha +3 more
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