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RISCriticality Calculations and Basic Sensitivity/Uncertainty Investigation of LR-0 Benchmark Core
Publisher: American Society of Mechanical Engineers (ASME)
Abstract: Three-dimensional Monte Carlo code KENO-VI of SCALE-6.2.2 code system was applied for criticality calculation of the LR-0 reactor core. A central module placed in the center of the core was filled by graphite, lithium ...
Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Concrete is an important structural material used in nuclear power plant (NPP) design. Due to relatively high amount of hydrogen as well as the presence of heavier elements, it also acts as a biological shielding. One of ...
Neutron Field Shaping Using Graphite for Reaction Rate Measurements
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Neutron field shaping is the suitable method for validation of cross section in various energy regions. By increasing the share of neutrons of a certain energy interval and decreasing the share of other, a reaction becomes ...
Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252Cf Source in Center
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Copper is an important material for the nuclear industry; therefore, the correct copper cross section are essential. This paper deals with benchmarking the fast neutron leakage spectrum from a copper block with an intense ...
Testing and Validation of Nuclear Fuel Composition Using SIMS Method
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Correct mathematical models of a reactor core in benchmarking of reactor physics experiments require detailed knowledge of exact isotopic composition of fuel pellets, especially the presence of neutron absorbers. Among ...
Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In this paper is described the concept of a 20 MW microreactor cooled by molten salts with the registered trademark of Energy Well. Energy Well reactor is designed to supply either electricity or heat, in remote areas or ...
Validation of the Fast Neutron Field in the Radial Channel of the VR-1 Reactor
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This work aims to characterize the neutron spectrum in the beam going out of the university research reactor (VR-1) using tubular-type of the nuclear fuel, version 4M (IRT-4M) fuel. Thanks to its variability, the core is ...
Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor
Publisher: American Society of Mechanical Engineers (ASME)
Abstract: With increasing needs of neutron detection in energy and homeland security sectors, there is an aim in the development of new suitable detection materials with possible n/g separation and also satisfactory resolution. This ...
The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This paper summarizes the issue of the validation of the silicon-filtered neutron beam transport in the deep neutron transport penetration experiment in iron. Iron is an essential structural material important for nuclear ...