Muhammad Asif

Directorate of Nuclear Power Engineering-Reactor

Pakistan Atomic Energy Commission (PAEC)

Cell: Email:

cell: +92-345-5352915 muhammadasif386@yahoo.co.uk

IAEA Technical Meeting on Technology Assessment of Small Modular Reactors for Near Term Deployment

Tunis, Tunisia 2-5 October 2017

� Present Energy Status

� Future Nuclear power Target of Pakistan

� Needs of SMRs in Pakistan

� Prospects of SMRs in Pakistan

� SMRs Potential Challenges of Pakistan

� SMRs Challenges and R&D Activities

� SMRs Core commissioning

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CHASHNUPPs

C1, C2, C3 & C4

kANUPPs

K1, K2 & K3

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S.

No.Name Location Capacity Type

Date of Commercial

Operation

1KANUPP-1

(K-1)Karachi 137/98 MWe PHWR Dec. 1972

2CHASHNUPP-1

(C-1)Chashma 325 MWe PWR Sep. 2000

3CHASHNUPP-2

(C-2)Chashma 340 MWe PWR May 2011

4CHASHNUPP-3

(C-3)Chashma 340 MWe PWR Dec. 2016

5CHASHNUPP-4

(C-4)Chashma 340 MWe PWR Sep. 2017

6KANUPP-2

(K-2)Karachi 1100 MWe PWR Under Construction

7KANUPP-3

(K-3)Karachi 1100 MWe PWR Under Construction

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Type MW Shares

Hydel 32,660 20.1%

Oil 7,760 4.8%

Gas 83,760 51.5%

Coal 19,910 12.2%

Nuclear 8,800 5.4%

Renewable 9,700 6.0%

Total 162,590 100.0%

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Electricity generation capacity in 2030

� Severe energy crisis and electricity shortfall about

7000 MWe in Summer .

� Plans for generation of 8800 MWe from nuclear contribution by 2030 and 40000 MWe from nuclear contribution by 2050.

� Large far-flung areas requiring small power plants

� Long coastal belt requiring clean water and energy

� Chilling Northern areas requiring district heating

� Industrial estates having reliable on-site energy requirements

� Technological advancement in safety achieved by SMRs

� Pakistan is water stress country

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� Modular design of SMRs can allow customized NPPs for different regions

� Shorter time for installation of SMRs due to prefabricated parts

� Energy sources for multipurpose application (Desalination, district heating, industrial steam etc.)

� Flexibility and add-on advantages to plan for growing energy demands

� Lesser overnight capital costs

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� Capacity to provide planning and operational assistance to embarking countries based on successful operation of conventional SMRs

� Prospects of collaboration for SMRs developer countries in design and deployment of SMRs

� Keeping abreast with the world in peaceful uses of nuclear energy

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� Long experience of successful nuclear power production

� Multi-technology nuclear reactors are in successful operation

� Complete nuclear power program is under safeguards of IAEA

� Construction of components and equipment for nuclear power plants

� Successful power generation program through PWRs

� Design Participation and Transfer of Technology for Chashma PWRs with China

� Involvement in design of nuclear power plants

� Comprehensive nuclear environment and nuclear industry

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� Design Conceptual to detailed stage

� Systems and equipment design

� Thermal hydraulics and core design

� PSA and accident analysis

� Innovative design solutions

� Testing Fuel qualification

� Systems and equipment qualification

� Equipment manufacturing

� Installation and erection

� Commissioning and operation

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� Site selections studies is in progress

� The public acceptance and demonstration

� Indigenous Design of SMRs

� SMR Technology selection (like ACP-100, CAREM, NuScale etc. )

� Passive Safety reliability

� Thermal hydraulic CFD simulations for design verification

� Small scale test rig for code verification

� Process system test rigs

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� Process system equipment deign

� Contain to some extent of 'first-of-a-kind'engineering systems and components, licensingand regulatory issues need to be addressed

� Integration of local industry for SMR production

� Supply chain management

� Long-term reliability may be a major technological & material challenge

� Nuclear Instrumentation

� Core commissioning and Startup Physics Tests

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� Stage-A (Pre-Operational Test)� Sub stage-A1 (Cold Performance Tests)� Sub stage-A2 (Hot Performance Tests)

� Stage-B (Fuel Loading, Initial criticality & Low Power Tests)� Sub stage-B1 (Fuel Loading)� Sub stage-B2 (Initial approach-to-criticality)� Sub stage-B3 (Low Power Tests)

� Stage-C (High Power Tests)

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� Nuclear Instrumentation (NI) & Detectors Calibration

� Initial Criticality Test� Low Power Core Physics Test

� Doppler Heating Point Measurement� MTC Measurement

� Critical Boron Concentration (CBC) Determination� Control Rod Worth Measurement

� Shutdown Margin Determination

� Physics Tests during Power Escalation� Heat Balance Test

� Power Coefficient Determination� Core Power Distribution Measurement

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� Reactor Startup Monitoring System (RSMS)

� Digital Reactivity Meter (DRM)

� Reactor Kinetics Measurement System

Indigenously developed nuclear measurement devices for core physics tests for Nuclear Power Plants & Research Reactors

The indigenous devices developed have been supplied to or used at

PARR-1, CHASNUPP-1/2/3/4 & KANUPP-1

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Applications� Monitoring of Initial Criticality

� Startup after each new reloading or long shutdown

Features / Functions

� Online prediction of criticality by means of critical;� Fuel Loading in the Core

� Control Rod Position� Boron Concentration

� Moderator Height

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Applications

� Used in Doppler Heating Point, MTC, CBC, RCCA Worth, Moderator Differential Worth, Reactivity coefficients measurements;

Features/Functions

� Real-time acquisition of neutron flux signals from plant NI

� Signal Filtering, moving averaging & first order filter � On-line measurement of fast reactivity transients in the core� State-of-the-art graphics features� Adjustable scaling of reactivity and flux display� Analogue outputs of flux and reactivity signals for recording on

pen chart recorders etc. � Data storage and off-line analysis capability

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DGNPE-Designed DRM DNPER Designed DRM

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File & Configuration Menu

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File &

Configuration

Menu

REACTIVITY/FLUX DISPLAY MENU

Methodology DRWM is an advanced method

to measure the rod worth. It is a dynamic process. In this process, the control bank inserts in to the reactor core at a maximum speed. The variation of dynamic reactivity will be measured, then the correction factors(SSF and DSF) will be used to correct the dynamic reactivity to static reactivity. And then ,the static bank worth will be finalized.

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Sequence� The reactor is critical with the controlling bank

inserted with a reactivity "bite" of ~60 pcm.

� The controlling bank is withdrawn to the All Rods Out (ARO) condition

� Once flux is near the nuclear heat level, then the test bank is inserted to the bottom in a continuous insertion

� Measurement data is based on the insertion only

� Once inserted, the bank is again withdrawn to the ARO condition and the next bank is selected

� Once the flux level is restored to near the nuclear heat level, the next bank is measured in the same manner

� After the testing of the last bank, the flux level is restored to the zero power testing range

� Static Spatial Factor (SSF) & Dynamic Spatial Factor (DSF) calculations

� Precise Dynamic Reactivity Meter development � Ex-core detector data acquisition� Filtration to eliminate background noise especially

in low Current zone� Background correction� Correction of dynamic reactivity by SSF and DSF

� Technical Scheme of DRWM implementation

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Technique

� The SRWM System acquires themeasured subcritical neutronmultiplication data from source rangedetectors at different sub-critical levelsduring startup.

� The data is inputted in the 3-D reactorphysics calculations algorithms, whichperform the fundamental modeextraction, spatial flux distribution andImportance correction factor by solvingthe eigenvalue and Fix Source problem.

� Plans have been finalized to include theremaining subcritical tests (MTC, CBC,SDM) in the package.

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Methodology

� During testing, control rods are withdrawn in themanner typical in preparing for Rod Drop TimeMeasurement

� During rod withdrawal from all-rods-in to all-rods-out, SRWM requires approximately 20state-points (i.e., hold points) where sourcerange count rate and reactor coolant system(RCS) temperature data are collected.

� The state-point sequence can be modified toallow for simultaneous SRWM and other Mode 3data collection (e.g., rod position indication).

� Upon reaching the all-rods-out condition, theSRWM data analysis system calculates totalcontrol rod worth and CBC from the data

collected at each state-point.

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Selection of Sub-Critical Stages

Core Modeling

Correction Factor Calculation

On-Line Neutron Counts Measurement

Sub-criticality Measurement; MTC & CBC

Neutron Counts Correction

Start

End