Results 21 to 30 of about 1,076,657 (296)
Energies, 2022 In line with Polish national activities and research programs investigating non-electrical-reactor use, the national GOSPOSTRATEG-HTR project was launched, aiming at the development of a novel pre-conceptual design of a High-Temperature Gas-cooled ...
Eleonora Skrzypek +6 more
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A MCNP simulation study of neutronic calculations of spallation targets [PDF]
Nuclear Technology and Radiation Protection, 2013 The accelerator driven system is an innovative reactor which is being considered as a dedicated high-level waste burner. The function of the spallation target in accelerator driven system is to convert the incident high-energy particle beam to low ...
Feghhi Seyed Amir Hossein +1 more
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Neutronics calculation of RTP core [PDF]
AIP Conference Proceedings, 2017 Reactor calculation and simulation are significantly important to ensure safety and better utilization of a research reactor. The Malaysian’s PUSPATI TRIGA Reactor (RTP) achieved initial criticality on June 28, 1982. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of ...
Mohamad Hairie B. Rabir +8 more
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A spatial dynamic model of the SHELF-M reactor facility with fuel and coolant temperature feedbacks [PDF]
Nuclear Energy and Technology, 2023 The evolution of nuclear power is inseparably linked with the development of breakthrough solutions in the field of economic development of new territories.
Denis A. Plotnikov +4 more
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Neutronics calculations for the TFTR neutron calorimeter [PDF]
, 1980 Neutronics anayses have been performed for an adiabatic neutron calorimeter consisting of a pure hydrocarbon moderator located just outside of the vacuum vessel of the Tokamak Fusion Test Reactor. One and two-dimensional neutronic analyses show that the incident fusion neutron fluence can be determined to +- 10% uncertainty by simply integrating ...
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Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly [PDF]
Nuclear Energy and Technology, 2022 This article presents the results of neutronic calculations of a VVER-1200 fuel assembly carried out using the multi-purpose three-dimensional continuous-energy Monte Carlo particle transport code Serpent 2.
Aleksey V. Lavronenko +3 more
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Neutron streaming studies along JET shielding penetrations
EPJ Web of Conferences, 2017 Neutronic benchmark experiments are carried out at JET aiming to assess the neutronic codes and data used in ITER analysis. Among other activities, experiments are performed in order to validate neutron streaming simulations along long penetrations in ...
Stamatelatos Ion E. +5 more
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Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library
Science and Technology of Nuclear Installations, 2021 In this paper, neutronic calculations and the core analysis of the VVER-1000 reactor were performed using MCNP6 code together with both ENDF/B-VII.1 and ENDF/B-VIII libraries.
Sonia M. Reda +3 more
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FUEL BURN-UP CALCULATION FOR WORKING CORE OF THE RSG-GAS RESEARCH REACTOR AT BATAN SERPONG
Jurnal Penelitian Fisika dan Aplikasinya, 2017 The neutronic parameters are required in the safety analysis of the RSG-GAS research reactor. The RSG-GAS research reactor, MTR (Material Testing Reactor) type is used for research and also in radioisotope production.
Tukiran Surbakti, Mochammad Imron
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Second order of average current nodal expansion method for the neutron noise simulation
Nuclear Engineering and Technology, 2021 The aim of this work is to prepare a neutron noise calculator based on the second order of average current nodal expansion method (ACNEM). Generally, nodal methods have the ability to fulfill the neutronic analysis with adequate precision using coarse ...
N. Poursalehi, A. Abed
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