An assessment of a VVER-1000 core during Turbo-Generator load reduction test using RELAP5/MOD3. 2 and WIMSD-5B/PARCSv2. 7
N Vahman, R Akbari-Jeyhouni, DR Ochbelagh… - Progress in Nuclear …, 2016 - Elsevier
Reactor dynamic tests, which are categorized as one of the power start-up test groups, are
the most complex tests during commissioning of the new nuclear power plants. This paper …
the most complex tests during commissioning of the new nuclear power plants. This paper …
[HTML][HTML] Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS
A Pourrostam, S Talebi, O Safarzadeh - Nuclear Engineering and …, 2021 - Elsevier
There has been a deep interest in trying to find better-performing fuel clad motivated by the
desire to decrease the likelihood of the reactor barrier failure like what happened in …
desire to decrease the likelihood of the reactor barrier failure like what happened in …
Study of neutron flux redistribution and shadowing effect in rod worth measurements with the rod drop experiment
GL Stefani, GES Carvalho, DAP Palma, MV Silva… - … Engineering and Design, 2023 - Elsevier
The main goal of this study is to quantify the neutron flux redistribution in detectors and the
shadowing effect between control rods by proposing an instrumental calibration factor for …
shadowing effect between control rods by proposing an instrumental calibration factor for …
Optimization of spatial structure designs of control rod using Monte Carlo code RMC
H Luo, M Li, S Huang, M Liu, K Wang - Frontiers in Energy, 2021 - Springer
Control rod is the most important approach to control reactivity in reactors, which is currently
a cluster of pins filled with boron carbide (B 4 C). In this case, neutrons are captured in the …
a cluster of pins filled with boron carbide (B 4 C). In this case, neutrons are captured in the …
Calculation of control rod worth and temperature reactivity coefficient of fuel and coolant with burn-up changes for VVRS-2 MWth nuclear reactor
M Rahgoshay, O Noori-Kalkhoran - Nuclear Engineering and Design, 2013 - Elsevier
One of the main issues of a nuclear reactor is safety and controlling system. This system is
designed to control the power of reactor and to prevent accidents. Control rods worth …
designed to control the power of reactor and to prevent accidents. Control rods worth …
Investigation of burnable poisons effects in reactor core design
AH Fadaei - Annals of Nuclear Energy, 2011 - Elsevier
Burnable absorber rods (BAR) and chemical shim are the main control poisons that are
used in the core for improving the reactor behavior and satisfying the safety criteria during …
used in the core for improving the reactor behavior and satisfying the safety criteria during …
Control rod worth calculations using deterministic and stochastic methods
M Varvayanni, P Savva, N Catsaros - Annals of Nuclear Energy, 2009 - Elsevier
Knowledge of the efficiency of a control rod to absorb excess reactivity in a nuclear reactor,
ie knowledge of its reactivity worth, is very important from many points of view. These include …
ie knowledge of its reactivity worth, is very important from many points of view. These include …
A new optimization method based on cellular automata for VVER-1000 nuclear reactor loading pattern
AH Fadaei, S Setayeshi - Annals of Nuclear Energy, 2009 - Elsevier
This paper presents a new and innovative optimization technique, which uses cellular
automata for solving multi-objective optimization problems. Due to its ability in simulating the …
automata for solving multi-objective optimization problems. Due to its ability in simulating the …
Group constants generation by Monte Carlo code MCS for LWR analysis
TDC Nguyen, D Lee - Computer Physics Communications, 2023 - Elsevier
This paper presents the generation of few-group constants using the Monte Carlo (MC) code
MCS for light-water reactor (LWR) analysis. The few-group constants are fed into the …
MCS for light-water reactor (LWR) analysis. The few-group constants are fed into the …
Control rod modeling and worth calculation for a typical 1100 MWe nuclear power plant using WIMS/D4 and CITATION
A typical 1100 MWe pressurized water reactor (PWR) is a second unit installed at the coastal
site of Pakistan. In this paper, verification analysis of reactivity control worth by means of rod …
site of Pakistan. In this paper, verification analysis of reactivity control worth by means of rod …