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Technical Brief

MCNP Simulation of In-Core Dose Rates for an Offline CANDU Reactor

[+] Author and Article Information
Jordan G. Gilbert

Arcadis Canada Inc. Richmond Hill, Ontario
jordan.gilbert@arcadis.com

Scott B. Nokleby

University of Ontario Institute of Technology Oshawa, Ontario
scott.nokleby@uoit.ca

Ed Waller

University of Ontario Institute of Technology Oshawa, Ontario
ed.waller@uoit.ca

1Corresponding author.

ASME doi:10.1115/1.4036354 History: Received November 08, 2016; Revised February 15, 2017

Abstract

Inspections of pressure tubes in CANDU reactors are a key part of maintaining safe operating conditions. The current inspection system, the Channel Inspection and Gauging Apparatus for Reactors (CIGAR), performs the job well but is limited by the fact that it can only inspect one channel at a time. A multidisciplinary team is currently developing a novel robotic inspection system. As part of this work, a Monte Carlo N-Particle (MCNP) model has been developed in order to predict the dose rates that the improved inspection system will be exposed to and, from this, predict the component lifetime. This MCNP model will be capable of predicting in-core dose rates at any location within the reactor, and as such could be used for other situations where the in-core dose rate needs to be know.Based on estimates from this model, it is expected that at 7 days after shutdown the improved inspection system could survive in core for approximately 7 hours, providing it uses a tungsten shield 2:5 cm in thickness around the integrated circuit components. This is expected to be sufficient to perform a single inspection. 1 Introduction and Background

Copyright (c) 2017 by ASME
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