Application of MCNP for neutronic calculations at VR-1 training reactor
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014The 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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Rod drop transient at VR-1 reactor – Experiment and Serpent transient calculation analysis
Annals of Nuclear Energy, 2020Abstract The rod drop experiment is an important transient in reactor operation. This study focuses on a comparison between experimental reactor physics data and respective calculation. The rod drop experiment was performed at the VR-1 reactor. A full core 3D model was used to calculate this transient using Serpent2.
Ondrej Novak +4 more
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Calibration of new I&C at VR-1 training reactor
Nuclear Engineering and Design, 2011The paper describes a calibration of the new instrumentation and control (I&C) at the VR-1 training reactor in Prague. The I&C uses uncompensated fission chambers for the power measurement that operate in a pulse or a DC current and a Campbell regime, according to the reactor power.
Martin Kropik, Monika Jurickova
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Characterization of mixed N/G beam of the VR-1 reactor
Annals of Nuclear Energy, 2018Abstract VR-1 is light water zero-power reactor using IRT-4 M fuel with nominal enrichment of 19.7 wt%, equipped with the radial channel being directly attached to the fuel. Enrichment at the top level of the low enriched uranium limit guarantees that the larger part of non-scattered neutrons in the spectrum is coming from 235U than in case of ...
Michal Košťál +11 more
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Investigation of mammoth remains using the neutron activation analysis at the Training Reactor VR-1
Applied Radiation and Isotopes, 2020At 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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Determination of the effective delayed neutron fraction for training reactor VR-1
Progress in Nuclear Energy, 2010Abstract This paper describes a methodology of effective delayed neutron fraction (βeff) determination for the VR-1 training reactor located at the Czech Technical University (CTU) in Prague. The methodology contains both experimental and computational elements.
Svetozár Michálek +6 more
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Neutronic design of instrumentation for thermal effects measurement on VR-1 reactor
2009 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications, 2009At the Czech Technical University (CTU) in Prague a new instrumentation for measurement of thermal effects is currently designed for the use on the training reactor VR-1 “Sparrow”. The instrumentation is designed to serve both for the purposes of education and training and RD in the latter case especially for the examination of possible precision and ...
Tomas Bily, Lubomir Sklenka
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Neutron field for activation experiments in horizontal channel of training reactor VR-1
Radiation Physics and Chemistry, 2014Abstract The experimental channels of nuclear reactors often serve for nuclear data measurement and validation. The dosimetry-foils activation technique was employed to measure neutron field parameters in the horizontal radial channel of the training reactor VR-1, and to test the possibility of using the reactor for scientific purposes.
Milan Stefanik +4 more
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Manual control during reactivity transients at the VR-1 reactor – I. Disturbance rejection
Nuclear Engineering and Design, 2017Abstract The description of human operator dynamic characteristics in mathematical terms compatible with control engineering practice is an essential prerequisite to the analytical treatment of manual reactor control systems. Safe reactor operation requires effective operator control through interaction with plant dynamics, manipulators and displays.
A.M. Darbyshire +3 more
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Validation of the Fast Neutron Field in the Radial Channel of the VR-1 Reactor
Journal of Nuclear Engineering and Radiation Science, 2020Abstract 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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