Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility
Science and Technology of Nuclear Installations, 2012 The OECD/NEA PSB-VVER project provided unique and useful experimental data for code validation from PSB-VVER test facility. This facility represents the scaled-down layout of the Russian-designed pressurized water reactor, namely, VVER-1000.
A. Del Nevo +8 more
doaj +1 more source
Optimization of the self-sufficient thorium fuel cycle for CANDU power reactors [PDF]
, 2008 The results of optimization calculations for CANDU reactors operating in the thorium cycle are presented in this paper. Calculations were performed to validate the feasibility of operating a heavy-water thermal neutron power reactor in a self-sufficient ...
Bergelson Boris R. +2 more
core +2 more sources
Ядерна фізика та енергетика, 2019 The paper presents the procedure developed at the Department of Radiation Material Science of INR NAS of Ukraine for longitudinal radiometric scanning of surveillance specimens of the Ukrainian reactor vessels and its joint application with ...
Yu. S. Gulchuk, L. I. Chyrko
doaj +1 more source
Vanquishing the computational cost of passive gamma emission tomography simulations leveraging physics-aware reduced order modeling. [PDF]
Sci Rep, 2023 Cavallini N +7 more
europepmc +1 more source
CODEX-B4C Experiment: Cored Degradation Test With Boron Carbide Control Rod KFKI-2003-01/G (2003) [PDF]
, 2003 The CODEX-B4C bundle test has been successfully performed on 25th May 2001 in the framework of the COLOSS project of the EU 5th FWP. The high temperature degradation of a VVER-1000 type bundle with B4C control rod was investigated with electrically ...
Balaskó, Márton +11 more
core
Localizing Perturbations in Pressurized Water Reactors Using One-Dimensional Deep Convolutional Neural Networks. [PDF]
Sensors (Basel), 2021 Pantera L +8 more
europepmc +1 more source
Structural and Parametric Optimization of S-CO2 Nuclear Power Plants. [PDF]
Entropy (Basel), 2021 Rogalev N +4 more
europepmc +1 more source
Calculation of static characteristics of linear step motors for control rod drives of nuclear reactors-an approximate approach [PDF]
, 1993 This paper describes an approximate method for calculating the static characteristics of linear step motors (LSM), being developed for control rod drives (CRD) in large nuclear reactors.
Ivanov, A., Khan, S.
core
Estimation of Control Rod Worth in a VVER-1000 Reactor using DRAGON4 and DONJON4
Nukleonika, 2014 One of the main issues in safety and control systems design of power and research reactors is to prevent accidents or reduce the imposed hazard. Control rod worth plays an important role in safety and control of reactors.
Saadatian-derakhshandeh Farahnaz +2 more
doaj +1 more source
Investigation of Coolant Mixing in Reactor VVER-1000
, 2011 We present an experimental investigation of coolant mixing in downcomer and lower plenum of VVER-1000 here. The arrangement of the problem, the methodology and results are discussed. Three groups of experiments simulating coolant mixing were executed: in conditions of RCP start-up, during natural circulation recovery in the course of SB LOCA and in ...
Lysenkov E. A. +11 more
openaire +3 more sources