Zobrazeno 1 - 10
of 796
pro vyhledávání: '"vver-1000"'
Publikováno v:
Âderna Fìzika ta Energetika, Vol 25, Iss 3, Pp 251-256 (2024)
The results of the validation of the code package MCPV for the calculation of radiation transport within VVER-1000 reactor type near-vessel space using a continuous-energy data library are presented. The validation is carried out based on the experim
Externí odkaz:
https://doaj.org/article/a29c719520c343c086b02271c1275777
Autor:
Navid Vahman, Reza Akbari
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 9, Pp 3826-3834 (2024)
The main purposes of start-up tests in nuclear power plants (NPPs) are to ensure safe and reliable operation, verify system functionality, comply with regulatory requirements, optimize performance, and establish a foundation for ongoing plant operati
Externí odkaz:
https://doaj.org/article/844b093cbc2d40f1994c63f6c0f00e96
Publikováno v:
Physics Open, Vol 19, Iss , Pp 100212- (2024)
This paper compares the ENDF/B-VIII.0 library for the MOX-fueled VVER-1000 pin cell benchmark with ENDF/B-VII.0 library using the ν-TRAC code and demonstrates the modeling capability of the code. ν-TRAC is a MOC-based code for simulating neutron tr
Externí odkaz:
https://doaj.org/article/ef2cb1a197834a299d597f2e66c304f3
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 39, Iss 1, Pp 12-20 (2024)
Burnable absorbers play an important role in nuclear reactor safety and exploring their effect on the reactor core behavior is an important issue in the design and operation of the reactor core. The aim of the present work was to discover the effe
Externí odkaz:
https://doaj.org/article/5a1f1ed65d46446495c8c6cee9a22b55
Autor:
V. V. Ilkovych
Publikováno v:
Âderna Fìzika ta Energetika, Vol 24, Iss 4, Pp 344-350 (2023)
A VVER-1000 reactor model using the Monte Carlo Serpent 2 code for core power distribution calculation is presented. The core and zones located near to the core were modeled in detail, without simplification. The assembly power distribution and axial
Externí odkaz:
https://doaj.org/article/15a24277543d428a8a9f0409b95f4a34
Publikováno v:
Nuclear Energy and Technology, Vol 9, Iss 4, Pp 215-225 (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. The results of neutronic analysis using the OpenMC Monte Carlo code for t
Externí odkaz:
https://doaj.org/article/9c2156a3521c44d88d7feb69198ce9da
Autor:
Mathilde Laot, Viviam Marques Pereira, Theo Bakker, Elio d’Agata, Oliver Martin, Murthy Kolluri
Publikováno v:
Metals, Vol 14, Iss 8, p 887 (2024)
Assessing the embrittlement and hardening of reactor pressure vessel steels is critical for the extension of the service lifetime of nuclear power plants. This paper summarises the tensile test results on the irradiation behaviour of realistic VVER-1
Externí odkaz:
https://doaj.org/article/5ab70b474b434830a6cd9c4c17b717a4
Autor:
Stepan Lys, Alexandr Kanyuka
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101565- (2024)
The operating conditions are analyzed, mechanical characteristics are calculated pertaining to the 4-year cycle fuel rods of VVER-1000. The fuel rod strength characteristics are considered as applied to steady-state and transient conditions of reacto
Externí odkaz:
https://doaj.org/article/2096857cbd184d5c9e495561ac0098f5
Autor:
O. M. Khotiaintseva, O. R. Trofymenko, V. M. Khotiaintsev, A. V. Nosovskyi, S. E. Sholomytsky, V. I. Gulik
Publikováno v:
Âderna Fìzika ta Energetika, Vol 24, Iss 3, Pp 231-238 (2023)
To calculate radiation fields in the concrete biological shield (CBS) of the VVER-1000 reactor in this work, we have developed and applied the Monte Carlo code Serpent simulation framework based on the variance reduction technique. We have quantified
Externí odkaz:
https://doaj.org/article/d0683a3cf88348369917b8e1f6e2d6be
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 2, Pp 756-768 (2023)
Neutron transport calculations are extremely challenging due to the high computational cost of large and complex problems. A multilevel octree grid algorithm (MLTG) of discrete ordinates method was developed to improve the modeling accuracy and simul
Externí odkaz:
https://doaj.org/article/7f10a34fb5554d41a834e490d2526534