Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
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|
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Article Number | 08003 | |
Number of page(s) | 8 | |
Section | Research Reactors and Facilities | |
DOI | https://doi.org/10.1051/epjconf/202124708003 | |
Published online | 22 February 2021 |
https://doi.org/10.1051/epjconf/202124708003
SENSITIVITY ANALYSIS OF STAINLESS STEEL REFLECTOR FOR VR-1 TRAINING REACTOR
Czech Technical University in Prague Department of Nuclear Reactors, V Holesovickach 2, 18000, Prague, Czech Republic
jan.frybort@fjfi.cvut.cz
lubomir.sklenka@fjfi.cvut.cz
Published online: 22 February 2021
Pressurized water reactors are typically surrounded in the radial direction by neutron reflectors made from stainless steel and water. These reflectors decrease neutron leakage and provide protection of pressure vessel from fast neutrons damaging its integrity. Such a radial reflector influences multiplication factor of the core and distribution of neutron flux and fission power inside the core. All these effects can be analyzed by full-core simulations using macroscopic constants. Methodology for generation of the macroscopic constants for non-fuel regions will be tested for new stainless steel reflectors at the VR-1 reactor. Rods from SS 304l material will be used for construction of radial reflectors for the VR-1 reactor. They will be design to generate sufficient measurable response in selected core characteristics. The study is focused on core power distribution and reactivity worth of absorbing rods in a VR-1 reactor core. The core typically consists of about 20 IRT-4M fuel assemblies and seven absorbing rods UR-70. Replacing water surrounding the core by several reflector assemblies containing stainless steel will influence leakage and distribution of neutrons inside the core. The current analysis deals with local effects and employs the sensitivity study to discover the nature of reflectors’ impact on the reactor core. These effects were studied even for several past VR-1 reactor core configurations. All calculations were carried out in Serpent2 Monte-Carlo code with various evaluated libraries: ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 data.
Key words: VR-1 Reactor / sensitivity / reflector / nuclear data / power distribution
© The Authors, published by EDP Sciences, 2021
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