B. Rouben McMaster University EP 4P03/6P Jan-Apr

Slides:



Advertisements
Similar presentations
RAID (Redundant Arrays of Independent Disks). Disk organization technique that manages a large number of disks, providing a view of a single disk of High.
Advertisements

Generic Pressurized Water Reactor (PWR): Safety Systems Overview
2014 January1 Xe-135 Effects in Reactor Operation B. Rouben McMaster University EP 4P03/6P Jan-Apr.
3: CANDU Reactivity Devices
Reactivity Coefficients
Lesson 17 HEAT GENERATION
Electrical, Control and Information Systems in the Enhanced CANDU 6 ® Electrical, Control and Information Systems in the Enhanced CANDU 6 ® Candu – Official.
Radiation Detectors / Particle Detectors
GENERATION III AND III+ NUCLEAR POWER PLANT DESIGNS ACR-1000 (Advanced CANDU Reactor) Dr. Şule Ergün Hacettepe University Department of Nuclear Engineering.
Issues Associated with the Development of Severe Accident Management Guidelines for CANDU Reactors Keith Dinnie Director, Risk Management Nuclear Safety.
2008 January1 CANDU Control Programs & Process Systems B. Rouben McMaster University EP 4P03/6P Jan-Apr.
INR Pitesti, D. Dobrea, L. Aioanei Task 4.3. Instrumentation Specifications 4. Core C& I devices 5. Primary coolant C&I devices Based on [1], [2] and [3],
Outlook for the Requirements of the Nuclear Power Plant Irradiation Test in China SONG DANRONG Nuclear Power Institute of China.
Graphs of Exponential and Logarithmic Functions
2015 January1 CANDU Detector Systems B. Rouben McMaster University EP 4P03/6P Jan-Apr.
Engineering Physics 4P03/6P03 Nuclear Power Plant Systems & Operation Hello! My name is Ben Rouben. I am the instructor for this course. For those who.
Advanced Test Reactor.
MODELLING OF THE VVER-440 REACTOR FOR DETERMINATION OF THE SPATIAL WEIGHT FUNCTION OF EX-CORE DETECTORS USING MCNP-4C2 CODE Gabriel Farkas, Vladimír Slugeň.
Department of Mechanical and Nuclear Engineering Reactor Dynamics and Fuel Management Group Comparative Analysis of PWR Core Wide and Hot Channel Calculations.
Pellet Charge Exchange Measurement in LHD & ITER ITPA Tohoku Univ. Tetsuo Ozaki, P.Goncharov, E.Veschev 1), N.Tamura, K.Sato, D.Kalinina and.
Building a CANDU reactor
1 8. One Function of Two Random Variables Given two random variables X and Y and a function g(x,y), we form a new random variable Z as Given the joint.
1 URBDP 591 A Lecture 12: Statistical Inference Objectives Sampling Distribution Principles of Hypothesis Testing Statistical Significance.
Regional Meeting on Applications of the Code of Conduct on Safety of Research Reactors Lisbon, Portugal, 2-6 November 2015 Diakov Oleksii, Institute for.
PHYSICS 225, 2 ND YEAR LAB NUCLEAR RADIATION DETECTORS G.F. West Thurs, Jan. 19.
Visual Computation I. Physiological Foundations
I & C.
COMPARATIVE ANALYSIS OF DIFFERENT METHODS OF MODELING OF MOST LOADED FUEL PIN IN TRANSIENTS Y.Ovdiyenko, V.Khalimonchuk, M. Ieremenko State Scientific.
Initiating Event Analysis IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop City, Country.
An overview of I&C Systems in APR 1400 Parvaiz Ahmed Khand December 28, 2007.
NEM433 Radiation Detection and Measurement Laboratory Fall 2013 Osman Şahin ÇELİKTEN.
© 2016 Global Market Insights, Inc. USA. All Rights Reserved Fuel Cell Market size worth $25.5bn by 2024 Tactical Communications Industry.
Sensors and Detectors - 2
y x Vincenzo Monaco, University of Torino HERA-LHC workshop 18/1/2005
BASIC PROFESSIONAL TRAINING COURSE Module XI Operational limits and conditions Case studies Version 1.0, May 2015 This material was prepared.
Date of download: 10/13/2017 Copyright © ASME. All rights reserved.
ESTIMATION.
Safety Instrumented Systems
GOVERNMENT ENGINEERING COLLEGE, BHAVNAGAR TOPIC : INTRODUCTION TO PRESSURE VESSELS Prepared By :- 1.Aal Akash Ansari Aarif.
Importance of Xe-135 in Reactor Operation
Sensors and Detectors - 2
Shipboard Electrical Distribution
Maximum and Minimum Nuclear Power Paths for the Republic of Korea
Date of download: 11/7/2017 Copyright © ASME. All rights reserved.
NEUTRON DIFFUSION THE CONTINUITY EQUATION
Safety Instrumented Systems
Engineering Physics 4P03/6P03
ACCURACY IN PERCENTILES
INTRODUCTION TO PRESSURE VESSELS
FlexfloTM Surge Relievers
Offerings for design safety from harmonization
observations of the muon bundles with IceCube
NRC Event Number – Event Date
Reactivity Coefficients
More on Fission Products
The digital read-out for the CSC system of the TOTEM experiment at LHC
One-Way Analysis of Variance
Environmental Safety Basic Emergency Response 5
Concurrency: Mutual Exclusion and Process Synchronization
Earthquake Magnitude Ahmed Elgamal
National Research Nuclear University MEPhI
Emergency Preparedness
8. One Function of Two Random Variables
АВЛИГАТАЙ ТЭМЦЭХ ҮНДЭСНИЙ ХӨТӨЛБӨР /танилцуулга/
UITF Conduct of Operations Review
Operation of Target Safety System (TSS)
Mikael Olsson Control Engineer
8. One Function of Two Random Variables
George D. Dickinson, Ian Parker  Biophysical Journal 
Presentation transcript:

B. Rouben McMaster University EP 4P03/6P03 2016 Jan-Apr CANDU ROP/NOP Systems B. Rouben McMaster University EP 4P03/6P03 2016 Jan-Apr 2016 January

Neutronic Protection Systems CANDU reactors are equipped with protection systems which detect an emergency situation and actuate the safety system(s). There is a separate neutronic protection system for each SDS. Each protection system is triplicated [has 3 separate “logic” (or “safety”) channels] and consists of out‑of‑core ion chambers and in‑core self‑powered detectors. Logic channels are D, E, and F for SDS-1 and G, H, and J for SDS-2. In each protection system, it suffices that 2 of 3 logic channels be “tripped” for the corresponding SDS to be actuated. 2016 January

Out-of-Core Ion Chambers There are 3 ion chambers in each protection system, 1 per logic channel. They are located at the outside surface of the calandria (see next Figure). Each ion chamber trips its logic channel when the measured rate of change of the logarithm of the flux , i.e. the quantity d(ln )/dt, exceeds a pre‑determined setpoint (e.g. 10% per second, i.e., 0.10 s‑1, for SDS-1 in the CANDU 6). 2016 January

Ion-Chamber Locations (eg. in C-6) 2016 January

In-Core ROP (NOP) Detectors There are also fast‑response (platinum or inconel) in‑core detectors in each protection system. In the CANDU 9: 54 in-core detectors for SDS-1, in vertical assemblies, and 48 for SDS-2, in horizontal assemblies (see examples in figure in next slide). The detectors are distributed among the various logic channels: channels D, E and F contain 11 or 12 detectors each, channels G, H, and J contain eight each. The detectors trip the logic channels on high neutron flux: when the reading of any 1 detector reaches a pre‑determined setpoint, the logic channel to which it is connected is tripped. The in-core-detector system is known as the Neutron‑Overpower‑Protection (NOP) or Regional-Overpower-Protection system (ROP). The detector trip setpoints are determined by an extensive analysis of hypothetical loss‑of‑regulation accidents. 2016 January

Location of Some SDS-1 (Vertical) and SDS-2 (Horizontal) NOP Detectors in Bruce A VFD16-R2D VFD20-R5D Assembly 6,16 9,13 17 8,12 4, 20 V F D 3 - R 1 F VFD3-R1F 2016 January

ROP Detector Readings in LOR Suppose there is a Loss of Regulation (LOR), with power rising. As the reactor power increases in the LOR, so will the flux increase at detector locations. The detector reading’s increase will depend on the detector’s location in core, relative to the flux peak, i.e., detectors may “see” the power increase to different degrees. The design of the detector locations, channelization, and trip setpoints is such that, in the event of a global or local power increase from a wide set of anticipated flux shapes, the system logic initiates a reactor shutdown before Onset of Intermittent Dryout (OID) is reached in any fuel channel. 2016 January

Race Between Channel Powers and Detector Readings For each ROP system, the objective is that 2 detectors in different safety channels reach their setpoint before any fuel channel reaches its critical channel power, taken here as the channel power at which fuel dryout is reached. Critical Channel Detector Power Trip Setpoint Reactor Power Increasing in a Loss of Regulation Channel Power Detector Reading 2016 January

The ROP design activity must determine: ROP Design Objective The ROP design activity must determine: The number of detectors required (for each ROP system) Their positions in the various available penetrations, to “see” a very wide range (hundreds) of anticipated flux/power shapes The detector setpoints The detector channelization so that the core is protected against an LOR leading to OID from any of the anticipated flux shapes 2016 January

Triplicated Tripping Logic The tripping logic of each triplicated protection system is as follows (see next Figure): One ion chamber can trip its logic channel on high log rate, or any 1 detector in the logic channel can trip the channel on high flux. Any 2 tripped channels will actuate the associated shutdown system. The triplicated tripping logic reduces the chance of a spurious trip, and allows the testing of the system on-line. 2016 January

Triplicated Tripping Logic for SDS-1 2016 January

END 2016 January