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0 An Instrumentation and Control for Loop Test 21-24 Aug. 2012 S.H. Ahn, J.T. Hong, C.Y. Joung, S.J. Park Neutron Utilization Technology Division

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Page 1: An Instrumentation and Control for Loop Test€¦ ·  · 2014-04-08An Instrumentation and Control for Loop Test 21-24 Aug. 2012 S.H. Ahn, ... Process Control System Data Acquisition

0

An Instrumentation and

Control for Loop Test

21-24 Aug. 2012

S.H. Ahn, J.T. Hong,

C.Y. Joung, S.J. Park

Neutron Utilization Technology Division

Page 2: An Instrumentation and Control for Loop Test€¦ ·  · 2014-04-08An Instrumentation and Control for Loop Test 21-24 Aug. 2012 S.H. Ahn, ... Process Control System Data Acquisition

1

Contents

Click to add Title 2 Pressurized Water Loop 2

Click to add Title 1 Instrumentation and Control System 3

Click to add Title 2 Test Rig & In-Pile Instrumentation 4

Click to add Title 1 Introduction of HANARO 1

Click to add Title 1 Conclusions 5

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2

Characteristics of HANARO

Type Open-tank-in-pool

Power 30 MWth

Coolant Light Water

Reflector Heavy water

Fuel Materials U3Si, 19.75% enriched

Absorber Hafnium

Reactor Building Confinement

Max Thermal Flux 5x1014 n/cm2s

Typical flux at port nose

2x1014 n/cm2s

7 horizontal ports & 36 vertical holes

Vertical hole for cold neutron source

Operation Cycle 24 days@5 weeks

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3

Fuel Test Loop

Material Irradiation

Neutron Activation Analysis

NTD

HANARO

Operation &

Development

Cold Neutron Beam

Radiography

Neutron Beam

Research

Neutron Irradiation Research

Public Welfare

Industrial

Application

RI Production

& Utilization

Reactor Operation

Experimental

Facility Operation

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4

Pressurized water loop

Simulates the steady-state operation condition of PWR

Irradiation Hole : IR1

Accommodate up to 3 pins of test fuel

Pressurized Water Loop

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Schematic Diagram of Loop

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Main Design Parameter of Loop

Parameters PWR test mode

Design Pressure, MPa 17.5

Design Temperature, ℃ 350

Operating Pressure, MPa 15.2

Operating Temperature

(IPS Inlet), ℃ 300.3

Operating Temperature

(IPS outlet), ℃ 312.0

Operating Flow, kg/s 1.65

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Instrumentation and Control (I&C) System

Nuclear

Safety

Related

Reactor

Shutdown

System

Loop

Shutdown

System

- Loop Protection Panels

(3 Channels)

- Loop Safety Control Panels

(2 trains)

- Loop Safety Indicator Panel

Loop Control System

Data Acquisition System

Non-

Nuclear

Safety

Related

Process

Control

System

Data

Acquisition

System

Safety Classification System Panels/System Composition

Reactor

Shutdown

Loop

Isolation

Control for

Non-Safety

Related Process

System

Data Acquisition,

Storage, Display

and Analysis for

Irradiation Test

Functions

- IEEE std-603

- 2/3 Logic

- Interconnection with

Existing RPS (Reactor

Protection System)

- Normal Operation at

HANARO Control Room

- Redundancy of Control

and Communication

Network

- HCS (Hybrid Control

System)

- AI/AO

- DI/DO

- Interface with SPND,

T/C, LVDT

Design

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Reactor Control Room : Normal Operation

Loop Control Room : Start-up, Maintenance

Composition of I&C System

Loop Safety

Indicator PNL

Loop Protection

PNL -1/2/3

Loop Safety Control

PNL-1/2

Measurement Signals

from Test Rig Electrical System Process System

Engineering

Station

Operator

Station

Loop

Control

Room

Reactor

Control

Room

Reactor Protection

System PNL-1/2/3

Loop Control System

Data Acquisition

System

DAS

Station

Operator

Station

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Signal Flow of Safety Related Control System

Reactor

Shutdown

Signal

FTL

Protection

Panels

Reactor

Protection

Panels

Loop

Safety

Control

Panels

FTL

Isolation

Signal

Loop

Safety

Indicator

Panel

Trip

Signals

from

FTL

Trip Signals from

HANARO

Loop Control Room Reactor Control Room

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Safety Related Control Panels

Design

Quality Class : Q

Seismic Category : I

IEEE std-603

- Single failure criterion/ Redundancy/

Independence/ Diversity/Fail-Safe/

Manual Initiation/ Channel Bypass/

Identification of Protective Action/

Interface with Non-Safety Related

System/Equipment Qualification. etc.

Manufacturing

Qualification

- Environmental Qualification : IEEE std-323

- Seismic Qualification : IEEE std-344

Loop Protection Panels

Loop Safety Control Panels &

Loop Safety Indicator Panel

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Non-Safety Related I&C System

Loop Control System

HCS (Hybrid Control System)

Redundancy of Control and

Communication Network

Normal Operation at Reactor Control

Room

Data Acquisition System

Data Acquisition, Storage, Display from

In-pile Instruments

Communication with Loop Control

System

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Remote Date Acquisition

Web based remote data acquisition

Data Acquisition System : Web Server

PC : Remote Area : Web Client

Independent Network

Real time data acquisition at remote PC

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IPS Including In-pile Instruments

Fuel centerline temp. Coolant temp. Neutron flux

Fission gas pressure

Test Fuel

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Installation at Rods Parameters (Instruments)

Rod 1

Fuel Rod Pressure (LVDT)

Centerline Temperature

(C-Type T/C)

Rod 2 Upper Part

Centerline Temperature

(C-Type T/C)

Lower Part -

Rod 3 Upper Part

Centerline Temperature

(C-Type T/C)

Lower Part -

Installation at Rig Position

Neutron Flux

(SPND) Upper/Middle/Lower

Coolant Temperature

(K-Type T/C) Upper/Middle/Lower

In-Pile Instrumentation

(3번 핵연료는 2번

핵연료와 동일)

Rod 1 Rod 2&3

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Manufacturing Procedure for Test Rig

Parts Manufacture

& Instruments Purchase

Inspection & Measurement

of Parts and Instruments

Assembling and Welding

of Fuel Rod for Test

Hole Drilling of Test Fuels,

Inspection/Cleansing

Assembling and Welding

of Fuel Rods

Test and Inspection of Fuel Rods

after Welding

Insulation Resistance

Test

Macrography

Dimension Inspection

Tensile Test

Organization Check

Helium Leakage Test

Test and Inspection of Fuel Rod

(for Test) after Welding

Parts Manufacture

(ASME Certificate of Authorization)

Fuel Rod Assembling to Test Rig

Instrument Cable Assembling

to Test Rig

Brazing

(ASME IV, Brazing Procedure)

Inspection

(ASME III, Authorized Inspection)

Test and Inspection of Test Rig

after Assembling

Insulation Resistance

Test

Dimension Inspection

Helium Leakage Test

Hydraulic

Test

Parts Assembling

Welding

Inspection

Manufacturing of Fuel Rods Manufacturing of Test Rig

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Manufacturing of Test Rig

Test and Inspection of Test Rig after Assembling

Manufacturing of Fuel Rods Manufacturing of Test Rig

Manufacturing of Test Rig

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Technology Development (1)

Sealing of instrumentation cable feed-through

(Brazing method, Mechanical sealing method)

Brazing

Instrumentation

cables

Mechanical Sealing

Sealing Part

Brazing

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Technology Development (2)

Rig with removable typed fuel rod for intermediate examination

Instrumented Fuel Rod Non-Instrumented Fuel Rod

Mechanical Joint Part

Welding technology for fuel rod and rig fabrication (TIG, Laser, etc.)

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Technology Development (3)

In-pile Instrumentation Technology

Drilling of pellet

Fuel centerline temp. measurement

Fission gas pressure measurement

Neutron flux measurement

Coolant temp.

Coolant flow

Fuel elongation measurement

Cladding swelling measurement

Connection of MI cable

etc.

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20

Conclusions

Instrumentation and Control for Pressurized Water Loop

Safety Related Control System

Non-safety Related Control System

- Loop Control System

- Data Acquisition System : connected with in-pile instruments

Technology Development in KAERI

Rig design and Fabrication

In-pile Instrumentation

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