Azraf Azman

Study of pipe thickness loss using a neutron radiography method

The purpose of this preliminary work is to study for thickness changes in objects using neutron radiography. In doing the project, the technique for the radiography was studied. The experiment was done at NUR-2 facility at TRIGA research reactor in Malaysian Nuclear Agency, Malaysia. Test samples of varying materials were used in this project. The samples were radiographed using direct technique. Radiographic images were recorded using Nitrocellulose film. The films obtained were digitized to processed and analyzed. Digital processing is done on the images using software Isee!. The images were processed to produce better image for analysis. The thickness changes in the image were measured to be compared with real thickness of the objects. From the data collected, percentages difference between measured and real thickness are below than 2%. This is considerably very low variation from original values. Therefore, verifying the neutron radiography technique used in this project.

Clinical comparison between external versus internal-external percutaneous transhepatic biliary drainage for malignant pancreaticobiliary obstruction

Results from this study are relevant toward implementation of safe and effective management of malignant pancreaticobiliary obstruction and ultimately lead to better patient outcomes. Comparison for unsuccessful drainage that proceeded to developed sepsis between EPTBD group and IEPTBD group showed approximately 27% more developed post-procedural sepsis after unsuccessful drainage in the IEPTBD group but it was not statistically significant (p value = 0.08).

Characterization of ZnBr2 solution as a liquid radiation shield for mobile hot cell window

The Mobile Hot Cell (MHC) has a viewing window which is usually made of almost transparent radiation shield material for the safety of MHC operators. Mobility is the main criterion for MHC; therefore liquid solution that can act as a radiation shield is usually selected as the window for MHC due to ease of transportation instead of a solid glass. As reported, Zinc Bromide (ZnBr2) solution was successfully used in viewing window for MHCs in South Africa and China. It was chosen due to its transparent solution, excellent performance as radiation shielding for gamma radiation, ease in preparation, handling, storage and treatment. Nevertheless, data and baseline studies on ZnBr2 as radiation shield are quite few. Therefore, a study on this matter was carried out. The preparation of ZnBr2 solution was processed at laboratory scale and the radiation shielding experiments were carried out using Cs-137 as radiation source. ZnBr2 solution was prepared by mixing ZnBr2 powder with distilled water. The mixing percentage of ZnBr2 powder, (%wt.) was varied to study the effect of density on the attenuation coefficient. The findings from this study will be used as a guideline in the production and management of ZnBr2 solution for MHC applications.The Mobile Hot Cell (MHC) has a viewing window which is usually made of almost transparent radiation shield material for the safety of MHC operators. Mobility is the main criterion for MHC; therefore liquid solution that can act as a radiation shield is usually selected as the window for MHC due to ease of transportation instead of a solid glass. As reported, Zinc Bromide (ZnBr2) solution was successfully used in viewing window for MHCs in South Africa and China. It was chosen due to its transparent solution, excellent performance as radiation shielding for gamma radiation, ease in preparation, handling, storage and treatment. Nevertheless, data and baseline studies on ZnBr2 as radiation shield are quite few. Therefore, a study on this matter was carried out. The preparation of ZnBr2 solution was processed at laboratory scale and the radiation shielding experiments were carried out using Cs-137 as radiation source. ZnBr2 solution was prepared by mixing ZnBr2 powder with distilled water. The mixing percent...

Web design and development for centralize area radiation monitoring system in Malaysian Nuclear Agency

One of the applications for radiation detector is area monitoring which is crucial for safety especially at a place where radiation source is involved. An environmental radiation monitoring system is a professional system that combines flexibility and ease of use for data collection and monitoring. Nowadays, with the growth of technology, devices and equipment can be connected to the network and Internet to enable online data acquisition. This technology enables data from the area monitoring devices to be transmitted to any place and location directly and faster. In Nuclear Malaysia, area radiation monitor devices are located at several selective locations such as laboratories and radiation facility. This system utilizes an Ethernet as a communication media for data acquisition of the area radiation levels from radiation detectors and stores the data at a server for recording and analysis. This paper discusses on the design and development of website that enable all user in Nuclear Malaysia to access and ...

Arduino based radiation survey meter

This paper presents the design of new digital radiation survey meter with LND7121 Geiger Muller tube detector and Atmega328P microcontroller. Development of the survey meter prototype is carried out on Arduino Uno platform. 16-bit Timer1 on the microcontroller is utilized as external pulse counter to produce count per second or CPS measurement. Conversion from CPS to dose rate technique is also performed by Arduino to display results in micro Sievert per hour (μSvhr−1). Conversion factor (CF) value for conversion of CPM to μSvhr−1 determined from manufacturer data sheet is compared with CF obtained from calibration procedure. The survey meter measurement results are found to be linear for dose rates below 3500 µSv/hr.

Stress analysis for wall structure in mobile hot cell design

Malaysian Nuclear Agency is developing a Mobile Hot Cell (MHC) in order to handle and manage Spent High Activity Radioactive Sources (SHARS) such as teletherapy heads and irradiators. At present, there are only two units of MHC in the world, in South Africa and China. Malaysian Mobile Hot cell is developed by Malaysian Nuclear Agency with the assistance of IAEA expert, based on the design of South Africa and China, but with improved features. Stress analysis has been performed on the design in order to fulfil the safety requirement in operation of MHC. This paper discusses the loading analysis effect from the sand to the MHC wall structure.

Cryostat system for investigation on new neutron moderator materials at reactor TRIGA PUSPATI

A simple continuous flow (SCF) cryostat was designed to investigate the neutron moderation of alumina in high temperature co-ceramic (HTCC) and polymeric materials such as Teflon under TRIGA neutron environment using a reflected neutron beam from a monochromator. Cooling of the cryostat will be carried out using liquid nitrogen. The cryostat will be built with an aluminum holder for moderator within stainless steel cylinder pipe. A copper thermocouple will be used as the temperature sensor to monitor the moderator temperature inside the cryostat holder. Initial measurements of neutron spectrum after neutron passing through the moderating materials have been carried out using a neutron spectrometer.

Proposal for grid computing for nuclear applications

The use of computer clusters for computational sciences including computational physics is vital as it provides computing power to crunch big numbers at a faster rate. In compute intensive applications that requires high resolution such as Monte Carlo simulation, the use of computer clusters in a grid form that supplies computational power to any nodes within the grid that needs computing power, has now become a necessity. In this paper, we described how the clusters running on a specific application could use resources within the grid, to run the applications to speed up the computing process.

Microstructural investigations of materials for low temperature co-fired ceramic (LTCC) based fuel cell using small angle neutron scattering

The concept and the realization fuel cell based on LTCC technology require the investigations of fired LTCC microstructures. The majority of the works involved using small angle neutron scattering studies on the microstructural of LTCC ceramic tape and development of neutron tomography for future tool to visualize channels inside the fired tape. Most SANS characterization were carried out at Smarter SANS instrument at BATAN, Indonesia. Standard sample for resolving tens of micron of object size were measured using simple neutron tomography setup utilizing monochromatic SANS beam at Malaysian Nuclear Agency. The initial microstructural findings indicates that organic additives shape the final microstructural of LTCC after firing with the glassy material possibly fill the space left by the burned organic additives. The tomography results showed that 40 micron size object can be differentiated. The conductor deposited on LTCC is preliminary investigated which will later be used as support for catalyst.

Micro-focused Small Angle Neutron Scattering and Imaging for Science and Engineering Using RTP--A Preliminary Study

Malaysian Nuclear Agency’s (Nuclear Malaysia) Small Angle Neutron Scattering (SANS) facility—(MYSANS)—is utilizing low flux of thermal neutron at the agency’s 1 MW TRIGA reactor. As the design nature of the 8 m SANS facility can allow object resolution in the range between 5 and 80 nm to be obtained. It can be used to study alloys, ceramics and polymers in certain area of problems that relate to samples containing strong scatterers or contrast. The current SANS system at Malaysian Nuclear Agency is only capable to measure Q in limited range with a PSD (128×128) fixed at 4 m from the sample. The existing reactor hall that incorporate this MYSANS facility has a layout that prohibits the rebuilding of MYSANS therefore the position between the wavelength selector (HOPG) and sample and the PSD cannot be increased for wider Q range. The flux of the neutron at current sample holder is very low which around 103 n/cm2/sec. Thus it is important to rebuild the MYSANS to maximize the utilization of neutron. Over the ...