Results 1 to 10 of about 351,427 (272)
Determining Reactor Flux from Xenon-136 and Cesium-135 in Spent Fuel [PDF]
, 2012 The ability to infer the reactor flux from spent fuel or seized fissile material would enhance the tools of nuclear forensics and nuclear nonproliferation significantly. We show that reactor flux can be inferred from the ratios of xenon-136 to xenon-134 and cesium-135 to cesium-137.
A.C. Hayes +11 more
arxiv +3 more sources
Nuclear Reactor Simulator [PDF]
, 1949 Abstract : The simulator is an electrical analogue computer. The idea of solving differential equations by the use of electrical models has become a widely accepted technique. If due consideration has been given to keeping the model similar to the physical phenomena described by the differential equations, the practical engineer has at his disposal a ...
J.M. Harrer
openalex +5 more sources
A simple model of reactor cores for reactor neutrino flux calculations for the KamLAND experiment [PDF]
Nucl.Instrum.Meth.A569:837-844,2006, 2006 KamLAND is a reactor neutrino oscillation experiment with a very long baseline. This experiment successfully measured oscillation phenomena of reactor antineutrinos coming mainly from 53 reactors in Japan. In order to extract the results, it is necessary to accurately calculate time-dependent antineutrino spectra from all the reactors.
A. Suzuki +10 more
arxiv +5 more sources
Search for the Neutrino Magnetic Moment in the Non-Equilibrium Reactor Antineutrino Energy Spectrum [PDF]
Phys.Atom.Nucl. 63 (2000) 1012-1015; Yad.Fiz. 63 (2000) 1087-1090, 1999 We study the time evolution of the typical nuclear reactor antineutrino energy spectrum during reactor ON period and the decay of the residual antineutrino spectrum after reactor is stopped. We find that relevant variations of the soft recoil electron spectra produced via weak and magnetic ${\widetilde {\nu}}_{e},e$ scattering process can play a ...
A. M. Bakalyarov +6 more
arxiv +5 more sources
Defected fuel rods identification in TRIGA Reactors: The experience at the ENEA Casaccia TRIGA RC-1 reactor [PDF]
EPJ Web of Conferences, 2023 Experience in running TRIGA reactors all around the world has shown that fuel cladding failures can occur. Fission products, especially in gaseous physical form, can exit the defected fuel rods being dispersed within the water primary coolant.
Lepore L. +6 more
doaj +1 more source
Effects of Hydrogen Bonding on Nuclear Data Development of Liquid Anhydrous HF [PDF]
EPJ Web of Conferences, 2023 Anhydrous Hydrogen Fluoride (HF) at high temperatures and pressures is used to process and manufacture nuclear fuel. As HF is often used directly with uranium, correct neutron thermal scattering cross sections are crucial to criticality safety ...
Ahmed Tanvir +2 more
doaj +1 more source
Neutronic conceptual design of Tehran Research Reactor using tubular fuel [PDF]
مجله علوم و فنون هستهای, 2022 The purpose of this paper is to investigate the possibility of using fuel with annular geometry (Tubular) in Tehran research reactor (TRR) from a neutronic perspective.
M. Hasanzadeh +5 more
doaj +1 more source
Science and Technology of Nuclear Installations, 2022 Steady-state and transient analysis of reactor core under Reactivity-Initiated Accident (RIA) conditions are important for reactor operation safety. The reactor dynamics are influenced by neutronic and thermal-hydraulic aspects of the core. In this study,
Surian Pinem +4 more
doaj +1 more source
Scientific Reports, 2023 This study conducted an evaluation of the corrosion behavior of an aluminum alloy utilized in the Isfahan Miniature Neutron Source Reactor (MNSR). The component analyzed, dry channel (DC), had been exposed to radiation for 12 years in a water environment
Mojtaba Bagherzadeh +5 more
doaj +1 more source
A SIMPLIFIED TWO-NODE COARSE-MESH FINITE DIFFERENCE METHOD FOR PIN-WISE CALCULATION WITH SP3 [PDF]
EPJ Web of Conferences, 2021 For accurate and efficient pin-by-pin core calculation of SP3 equations, a simplified two-node Coarse Mesh Finite Difference (CMFD) method with the nonlinear iterative strategy is proposed.
Zhao Wenbo +8 more
doaj +1 more source