Studies of fuel loading pattern optimization for a typical pressurized water reactor (PWR) using improved pivot particle swarm method

2012 ◽  
Vol 50 ◽  
pp. 117-125 ◽  
Author(s):  
Shichang Liu ◽  
Jiejin Cai
Keyword(s):  
Particle Swarm ◽  
Pressurized Water Reactor ◽  
Fuel Loading ◽  
Pressurized Water ◽  
Water Reactor ◽  
Loading Pattern ◽  
Particle Swarm Method

Research on the Loading Pattern of Reactor Core With MOX Fuel in the First Cycle

2012 ◽  
Author(s):  
Tianqi Zhang ◽  
Shihe Yu ◽  
Xinrong Cao
Keyword(s):  
Cross Section ◽  
Reactor Core ◽  
Fuel Utilization ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Loading Pattern ◽  
Mox Fuel ◽  
Initial Cycle ◽  
Calculation Code

In order to research the performance of Pressurized Water Reactor (PWR) with 1/3 MOX fuel in the initial cycle, this paper serves Qinshan II reactor core as the reference core to design suitable MOX assemblies and study relevant core properties. The analyses documented within use assembly cross section calculation code CASMO-4 and core calculation code SIMULATE-3 studied by Studsvik. The purpose of this paper is to demonstrate that the Qinshan II reactor is capable of complying with the requirement for MOX fuel utilization without significant changes to the design of the plant. Several impacts on key physics parameters and safety analysis assumptions, introduced by MOX, are discussing in the paper.

scholarly journals Thorium based fuel loading pattern for PWR reactor

2019 ◽  
Vol 108 ◽  
pp. 01028 ◽  
Author(s):  
Mikolaj Oettingen
Keyword(s):  
Monte Carlo ◽  
Numerical Model ◽  
Pressurized Water Reactor ◽  
Fuel Management ◽  
Fuel Loading ◽  
Pressurized Water ◽  
Loading Pattern ◽  
The Core ◽  
Continuous Energy ◽  
Numerical Tools

The Monte Carlo Continuous Energy Burnup Code was used for numerical simulations of the pressurized water reactor (PWR) with mixed U-Th fuel. The thorium fuel was introduce to the core of the Westinghouse 4-loop PWR in order to investigate the time evolutions of fissile 233U, 235U, 239Pu, 241Pu and of fertile 232Th and 238U. The core loading pattern was designed using the Whole Assembly Seed and Blanket (WASB) approach. The following calculations show the feasibility of the proposed incore fuel management patter using the available numerical tools, developed numerical model and methods.

Particle Swarm Optimization applied to the nuclear reload problem of a Pressurized Water Reactor

2009 ◽  
Vol 51 (2) ◽  
pp. 319-326 ◽  
Author(s):  
Anderson Alvarenga de Moura Meneses ◽  
Marcelo Dornellas Machado ◽  
Roberto Schirru
Keyword(s):  
Particle Swarm Optimization ◽  
Particle Swarm ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Swarm Optimization ◽  
Water Reactor
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