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Applications to CANDU Reactors

2012
This chapter gives examples of how engineering data of DHC initiation, growth rate, and solvus determinations, supported by theoretical models, and associated underlying property measurements and analyses, are applied in integrity assessments of pressure tubes of CANDU reactors. Examples are given of (1) planar and volumetric flaw assessment approaches
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Fuel management in CANDU reactors

Annals of Nuclear Energy, 1976
Abstract CANDU fuel management differs completely from that in LWR's. On-power refuelling of the pressurized fuel channels with short (50 cm) fuel bundles is a continuing function of reactor operations and leads rapidly to equilibrium core conditions, refuelling rate, and fuel burn-up.
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CANDU Fuel—Power Ramp Performance Criteria

Nuclear Technology, 1977
Extensive fuel performance data obtained from Canadian Deuterium Uranium (CANDU) power reactors and experimental reactors are analyzed. Various modes of power ramping that cause fuel defects are identified, and fuel defect criteria are derived. The probability of a defect occurring in a power ramp is found to depend on the magnitude of the ramped power,
W. J. Penn, R. K. Lo, J. C. Wood
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Thermal Fatigue in CANDU Stations

Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 2009
The risk of thermal fatigue, and the resulting pressure boundary failures, have resulted in a significant amount of research in the Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR) communities in the past two decades. Thermal stresses arising from thermal stratification phenomena are typically not taken into account in design ...
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การพัฒนาเครือข่ายนิวรอลสำหรับแสดงภาวะทรานเซียนต์ของแบบจำลองโรงไฟฟ้านิวเคลียร์ CANDU-9

การประยุกต์ใช้เทคโนโลยีของเครือข่ายนิวรอลอย่างหนึ่งก็คือ การพัฒนาเครือข่ายนิวรอลชนิด Self-Organizing Feature Maps (SOFM) ขึ้นมาโดยมีวัตถุประสงค์เพื่อใช้แสดงฟังก์ชัน (Function) ที่ผิดปกติในโรงไฟฟ้าพลังงานนิวเคลียร์อันเนื่องมาจากภาวะทรานเซียนต์ที่ไม่ต้องการ แบบจำลองโรงไฟฟ้านิวเคลียร์แคนดู-9 (CANDU-9 Nuclear Power Plant Simulator) ได้ถูกใช้เป็นที่ฝ ...
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Development of CANDU-specific operational intervention levels

Annals of Nuclear Energy, 2022
Luke Lebel, Andrew Morreale
exaly  

On the Amount of Moderation in the CANDU Lattice

Nuclear Technology, 2021
Benjamin Rouben
exaly  

Development and Evaluation of Polaris CANDU Geometry Modelling and of TRACE_Mac/PARCS_Mac Coupling with RRS for CANDU Analysis

2023
McMaster University DOCTOR OF PHILOSOPHY (2022) Hamilton, Ontario (Engineering Physics) TITLE: Development and Evaluation of Polaris CANDU Geometry Modelling and of TRACE_Mac/PARCS_Mac Coupling with RRS for CANDU Analysis AUTHOR: Simon Younan, M.A.Sc. (McMaster University), B.Eng. (McMaster University) SUPERVISOR: Dr.
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Power Transient in a CANDU Reactor

1978
In this report, the effectiveness of a proposed Shutoff Rod System a CANDU Reactor was investigated. A full core simulation was done, to study the neutronic power transient following a change in coolant conditions.
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