Results 141 to 150 of about 22,450 (171)
Validation of the Fast Neutron Field in the Radial Channel of the VR-1 Reactor
Journal of Nuclear Engineering and Radiation Science, 2020 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 often rearranged to fulfill different research tasks.
Evžen Losa +9 more
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Equipment for neutron measurements at VR–1 Sparrow training reactor
Applied Radiation and Isotopes, 2010 The VR-1 sparrow reactor is an experimental nuclear facility for training, student education and teaching purposes. The sparrow reactor is an educational platform for the basic experiments at the reactor physic and dosimetry. The aim of this article is to describe the new experimental equipment EMK310 features and possibilities for neutron detection by
Antonin, Kolros +3 more
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Application of MCNP for neutronic calculations at VR-1 training reactor
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014 The paper presents utilization of Monte Carlo MCNP transport code for neutronic calculations of training reactor VR-1. Results of calculations are compared with results of measurements realized during last few critical experiments with various reactor core configurations. Very good agreement between calculations and measurements is observed.
Ondřej Huml, Jan Rataj, Tomáš Bílý
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Validation of the Serpent2 code for the VR-1 reactor core calculation
2020 21st International Scientific Conference on Electric Power Engineering (EPE), 2020 The VR-1 reactor core safety characteristics calculations are performed by standardized MCNP code, however due to license requirements, it is desired to replace it by the Serpent2 code. In order to do that, Serpent2 calculation must be standardized by State office of nuclear safety.
Ondrej Novak, Jan Frybort
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Neutron Activation Analysis of Environmental Samples at the Training Reactor VR-1
Journal of Nuclear Engineering and Radiation ScienceAbstract Described research work is focused on the study of environmental pollution in the Czech Republic using an instrumental neutron activation analysis (INAA). The samples of mosses and alluvial soils were irradiated at the VR-1 training reactor utilizing a nondestructive (instrumental) method of NAA at the Czech Technical University
Alena Krechlerova, Milan Stefanik
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Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 2009 The research reactor VR-1 is operated by Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University (CTU) in Prague. It is a pool-type, light-water reactor, with low enriched uranium. Maximum thermal power is 1kW (equal to 1·108 impulses/second when compared with reactors with higher power). Research on VR-1 reactor is mainly used
Marija Mileticˇ
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Investigation of mammoth remains using the neutron activation analysis at the Training Reactor VR-1
Applied Radiation and Isotopes, 2020 At the time when the importance of the interdisciplinary research increases, the nuclear analytical techniques supported by the small research reactors represent a useful tool for investigation of human society, culture, history etc. The historical, archaeological, and palaeontological samples and objects of cultural heritage can be easily studied ...
Milan Stefanik +2 more
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Annals of Nuclear Energy, 2019 Abstract Kinetics parameters are of high importance for reactor transient analyses. Similarly, they play an important role in many experimental reactor techniques, especially in techniques for determination of reactivity (such as Source Jerk, Rod Drop, or Source Multiplication method).
Tomas Bily +3 more
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Deterministic and stochastic neutron cross-section generation for PARCS applied to VR-1 reactor
2016 17th International Scientific Conference on Electric Power Engineering (EPE), 2016 The VR-1 reactor operated by the Czech Technical University in Prague was utilized for a study of a macroscopic cross-sections homogenization performed by deterministic (SCALE 6.1.2 — Triton) and stochastic (Serpent 2.1.24) codes. These cross-sections are subsequently imported into a fixed source problem solved by the three-dimensional reactor core ...
Filip Fejt
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TRAINING REACTOR VR-1 NEUTRON SPECTRUM DETERMINATION
Reactor Dosimetry State of the Art 2008, 2009 M. VINS, A. KOLROS, K. KATOVSKY
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