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IAEA Technical Meeting and TRTR Conference on Research Reactor Ageing Management, Refurbishment and Modernization, Brewster, Massachusetts, USA, 04-10-2015

Measurement of in-core thermal neutron fluxes using self powered neutron detector

at TRIGA MARK II PUSPATI Reactor

Muhammad Rawi MOHAMED ZIN, Zarina MASOOD Mohd Ashhar KHALID, Abdul Aziz RAMLI, Abi Muttaqin Jalal Bayar, Na’im

Syauqi, Hairie Rabir, Technical Programme, Technical Services Division, Reactor Technology Centre

Malaysian Nuclear Agency


CONTENTS

Major works done under ageing management

Ageing Management System

Background of Reactor TRIGA PUSPATI

Introduction to Nuclear Malaysia

Measurement of thermal neutron flux in RTP Core

Acknowledgement

Summary and future works


Coordination and management of nuclear affairs at national and international levels and as liaison agency for the International Atomic Energy Agency. National Authority for the Comprehensive Nuclear Test- Ban Treaty (CTBT) since 1 998

Introduction to Nuclear Malaysia

Conduct research and development (R&D), services and training in nuclear technology for national development. Promote the application, transfer and commercialization of nuclear technology

Functions


Organization of Nuclear Malaysia Director General

Research & Development

Medical Technology

Industrial Technology

Radiation Processing

Agrotech & Bioscience

Waste & Environmental Technology (BAS)

Research & Innovation Management

Technical Service

Radiation Safety & Health (BKS)

Reactor Technology Centre (RTC)

Technical Support

Engineering

Commercialisation & Technology Planning

Irradiation Facilities

Technology Commercialisation

• SSDL • Training Centre

Management

Planning & International

Relations

Administration

Human Resource Development

Information Management


Reactor TRIGA PUSPATI (RTP)

LEU Fuel: UZrH Control Rod: B4C Coolant/Moderator: H2O Reflector: Graphite No Fuel: 112 No CR: 4 Facilities: 4 beamport, Incore PTS, Rotary Rack, DNA, Dry Tube

Utilization: Training & Education R & D Isotope Production Public Awareness Programme

Construction began on 19 Sept 1972

Operational since 28 June 1982


Maintenance Programme And Training Analysis

Ageing Management Program

Documentation Recording/Keeping

Implementing/Monitoring Inspection Audit

In-service Inspection

Integrated Management System


Year System Type of work done 1986 Rack & Pinion gear (Rotary Rack) Repaired 1989 Primary pump Repaired and upgraded to 3 units 1990 Console Chart Recorder Replaced 1990 Regulating rod drive mechanism Replaced 1991 Uninterrupted Power Supply Replaced 1994 Fission chamber Replaced 1994 Heat Exchanger Refurbished (12 tubes plugged) 1995 Secondary Cooling System Cooling Tower replaced 1999 Ventilation System Refurbished 2000 SANS Facilities Refurbished 2000 Reactor Instrumentation Repaired 2004 Stack Monitoring System Replaced 2007 Heat Exchanger Plan to replace the tubes 2007-2010

Consol Plan to Upgrad

Ageing Management Program of RTP (AMPRTP)

Major works done under AMPRTP from 1986 to 2010


Visual Inspection of Core Grid Plate

The visual inspection of the core grid plate was carried out using an underwater camera. However, the radiation level was too high to get a close-up view hence, a different method was suggested. Therefore, the boroscopic technique was implemented for a visual inspection.Visual inspection of the top grid plate. It can be seen that there are no obvious signs of damage. The boroscope could not be inserted into the bottom to visualize the bottom grid plate.


Replacement work of primary cooling system

Tube type heat exchanger (old)

Plate type heat exchanger (new)

SCADA System (new)


Modernization of Control Console

Transformation from analogue to digital control mechanism


Underwater Inspection of RTP pool tank using in-house UT Device


Calibration plate used for UT underwater Inspection of RTP pool tank


Measurement locations for UT underwater Inspection of RTP pool tank


Additional SPND signal components; A. I(n,Beta emitter) B. I(n,beta insulator) C. I(n,beta collector) D. I(n,beta surroundings) E. I(n,gamma,e) F. I(gamma,e)

For a vanadium SPND, the major component is due to neutron capture by the vanadium nuclei (mainly the vanadium-51 isotopes) in the emitter. This leads to the formation of vanadium-52 isotopes, which are unstable and decay with a characteristic half-life of 3.75 minutes towards chromium-52. During this decay, a beta ray is emitted (as well as some gamma rays). This beta (actually a fast electron) has a significant probability to escape from the emitter and reach the collector after crossing the insulator. This corresponds to a charge transfer from emitter to collector, which can be measured as a current when externally closing the circuit (with an ampere meter).

Source of current induced by neutron in Vanadium SPND


Neutron Fluxes Monitoring Facility (Self Powered Neutron Detector)

The detector tip is made of Vanadium, fixed onto the Aluminium holder which inserted into the fluxes hole (H1).


16

Thermal neutron fluxes measured at H1 using SPND1

10 kW

50 kW

100 kW

200 kW


17

Thermal neutron fluxes measured at H1 using SPND4

10 kW

50 kW

100 kW

200 kW


Summary on recent works done and way forwards

• Upgrading of cooling system and • development of spent fuel pool

• Installation of new fission chamber

• Installation new ventilation • Upgrading electrical System of RTP

• New fuel transfer cask • Commissioning of SPND* in RTP Core

Get New digital Reactor

Control Console

Upgrading of Heat Exchanger

2010

2014

2015

…..2016

Primary cooling system upgrading

SPND : Self Powered Neutron Detector

• Aim : Enhance safety and utilization.

• Preparation for more active in education and training to support nuclear power program.

• Preparation for more RND activities related with research reactor utilization.


Acknowledgements

•Thanks to the IAEA for all continuous supports. •Thanks to the Government of Malaysia in providing funds to support activities at RTP.


Thank you very much for kind attention

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