Quantum evolutionary algorithm and tabu search in pressurized water reactor loading pattern design

2016 ◽  
Vol 94 ◽  
pp. 773-782 ◽  
Author(s):  
Shun-Chi Wu ◽  
Tsung-Han Chan ◽  
Ming-Shao Hsieh ◽  
Chaung Lin
Keyword(s):  
Tabu Search ◽  
Evolutionary Algorithm ◽  
Pressurized Water Reactor ◽  
Pattern Design ◽  
Pressurized Water ◽  
Water Reactor ◽  
Loading Pattern

Pressurized Water Reactor Loading Pattern Design Using the Simple Tabu Search

1998 ◽  
Vol 129 (1) ◽  
pp. 61-71 ◽  
Author(s):  
Chaung Lin ◽  
Jiing-Iuan Yang ◽  
Kuan-Jan Lin ◽  
Zheng-De Wang
Keyword(s):  
Tabu Search ◽  
Pressurized Water Reactor ◽  
Pattern Design ◽  
Pressurized Water ◽  
Water Reactor ◽  
Loading Pattern

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.

Implementation of RAVE™ (To a Reload)

2009 ◽  
Author(s):  
Cenk Gu¨ler ◽  
Serhat Lider
Keyword(s):  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Loading Pattern ◽  
Safety Accident ◽  
First Time

Westinghouse 3D Transient Neutronics methodology, RAVE™, has been implemented for the first time for licensing basis analysis of a Westinghouse 2-Loop type Pressurized Water Reactor (PWR). Westinghouse is using the traditional reload methodology for its fleet by utilizing a bounding approach. Safety limits are defined at the beginning of the process by using bounding values. These limits are then checked for every reload and they are shown then there are no violations to those limits therefore the safety calculations are still acceptable for the new loading pattern. This approach eliminates repeating safety/accident calculations for each reload. A new reload methodology was developed which utilizes similar safety reload methodology.

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