Results 1 to 10 of about 625 (112)
Evaluating machine learned nuclear data precision in full core nuclear reactor Monte Carlo neutronics and computational efficiency analyses [PDF]
Scientific ReportsThis study evaluates the novel machine learning based reduction of cross-sections and energy grid of continuous-energy nuclear data for one year full core Monte Carlo criticality and burn-up analysis using OpenMC.
Alexander Hashemi +2 more
doaj +2 more sources
SERPENT/SUBCHANFLOW COUPLED BURNUP CALCULATIONS FOR VVER FUEL ASSEMBLIES [PDF]
EPJ Web of Conferences, 2021 The continuous improvement in nuclear industry safety standards and reactor designers’ and operators’ commercial goals represent a push for the development of highly accurate methodologies in reactor physics.
Ferraro Diego +6 more
doaj +1 more source
3-D COUPLED SIMULATION OF A VVER 1000 WITH PARCS/ATHLET [PDF]
EPJ Web of Conferences, 2021 A new OECD/NEA benchmark entitled “Reactivity compensation with diluted boron by stepwise insertion of control rod cluster” is starting. This benchmark, based on high quality measurements performed at the NPP Rostov Unit 2, aims to validate and assess ...
Henry Romain +3 more
doaj +1 more source
A SUBCHANNEL COARSENING METHOD FOR Serpent2-SUBCHANFLOW APPLIED TO A FULL-CORE VVER PROBLEM [PDF]
EPJ Web of Conferences, 2021 This work presents a methodology to coarsen subchannel models to accelerate largescale Serpent2-SUBCHANFLOW calculations. The method is based on first building a fully detailed subchannel model and then combining subchannels into larger channels with ...
García Manuel +7 more
doaj +1 more source
COUPLING OF nTRACER TO COBRA-TF FOR HIGH-FIDELITY ANALYSIS OF VVERs [PDF]
EPJ Web of Conferences, 2021 Paul Scherrer Institut is developing a high-resolution multi-physics core solver for VVER analysis. This work presents the preliminary stages of the development, specifically the coupling of the 3D pin-by-pin neutronic solver nTRACER to the sub-channel ...
Papadionysiou Marianna +6 more
doaj +1 more source
Neutronic calculations for the VVER-1000 MOX core computational benchmark using the OpenMC code [PDF]
Nuclear Energy and Technology, 2023 The goal of this study is to perform neutronic calculations of the VVER-1000 MOX core computational benchmarks with an OpenMC code along with ENDF/B-VII.1 nuclear data library.
Md Imtiaj Hossain +3 more
doaj +3 more sources
Известия высших учебных заведений и энергетических объединенний СНГ: Энергетика, 2022 The hydrogen removal system ensures hydrogen safety. At a VVER nuclear power plant, it consists of passive catalytic hydrogen recombiners. The calculation of devices is of great importance for safety justification, since the complex conditions of an ...
V. V. Sorokin
doaj +1 more source
Numerical simulation on heat transfer of VVER core cather
He jishu, 2023 BackgroundThe core corium may melt through the reactor pressure vessel wall then lead to the failure of the second barrier during a serious accident. Core catcher can collect and cool the corium and prevent the development of severe accident.PurposeThis ...
ZHU Guangyu +4 more
doaj +1 more source
Известия высших учебных заведений и энергетических объединенний СНГ: Энергетика, 2023 An autonomous system of passive removal of residual heat (PRRHS) of a reactor installation with VVER designed to ensure the safety of nuclear power plants in an accident with complete long-term blackout is considered.
I. I Sviridenko, D. V. Shevelyov
doaj +1 more source
Accounting of the vver-1200 overload influence for fission products activities calculating
Весці Нацыянальнай акадэміі навук Беларусі: Серыя фізіка-тэхнічных навук, 2020 Current work is aimed at the analysis of the fission products decay influence during fuel reloading, when calculating the accumulated fission products activity for the VVER-1200 reactor fuel campaign. The Bateman problem solution based technique was used
A. M. Petrovski +3 more
doaj +1 more source