Many times a year natural gas transmission and distribution companies need to make new connections to pipelines to expand or modify their existing system through hot tapping procedure. This procedure involves the installation of a new pipeline connection while the pipeline remains in service, flowing natural gas under pressure. The hot tap procedure includes attaching a branch connection and valve on the outside of an operating pipeline, and then cutting out the pipe-line wall within the branch and removing the wall section, which is called object of coupon through the valve. During the hot tapping process a critical problems occurred when a coupon fell into the mother pipeline. To overcome this problem, a gamma-ray absorption technique was chosen whereby a mapping technique will be done to detect the coupon position. The technique is non-destructive as it applies Co-60 (5mCi) as a radioisotope sealed source to emit gamma radiation and a NaI(Tl) scintillation as detector. The result provided a visible representation of density profile inside pipeline where the coupon location can be located. This paper provides the detail of the technique used and presents the result obtained.
In industrial plants such as electricity generating, petroleum, chemical and petrochemical plants, pipelines are used extensively to transport liquid from one location to another. In radiation vulcanization of natural rubber latex (RVNRL) plants, pipelines are also used to transport latex to storage tank. During one of its maintenance activities, a pipeline intelligent gauge (PIG) that was used to monitor pipe integrity jammed inside the pipe causing interruption to its operation or loading activities. Sealed source technology was utilized to determine the location of jammed PIG in the pipeline. Fast neutrons from a 50 mCi Americium Beryllium (AmBe241), with energy range between 0.5 to11 MeV, were used for the study. Helium 3 (He3) detector was used to detect slow neutrons having a range of energy of 30 eV- 0.5 MeV. The investigation was carried out using neutron backscatter technique scanner. By adopting back-scattered technique, the location of jammed PIG in the pipeline has been successfully determined.
Detection and analysis of resin is particularly significant since the commercial value of agarwood is related to the quantity of resins that are present. This article explores the potential of a scanning electron microscope in combination with new non-destructive 3D visualization technique, X-ray micro-computed tomography, as imaging tools to visualize micro-structure resin in agarwood. These techniques were used to compare two samples of agarwood chips: high grade and low grade. From the results, it can be concluded that a wood cell filled with resin deposit have a higher attenuation. It can be shown that the combination of scanning electron microscopy and micro-CT can offer high resolution images concerning the localization and structure of resin inside Agarwood. While the second allows the 3D investigation of internal structure of agarwood, the first technique can provide details 2D morphological information. These imaging techniques, although sophisticated can be used for standard development especially in grading of agarwoodlbr commercial activities.
Flow measurement is a critical element for liquid resources monitoring for various applications in many industrial systems. The purposes of the study are to determine the flow rate of liquid system in flow rig using radiotracer techniques and to compare the result with that obtained by the conventional flow meters. The flow rig consists of 58.7m long and 20cm diameter pipeline that can accommodate about 0.296m3 of liquid. Tap water was used as liquid flow in pipeline and conventional flow meters were also installed at the flow rig. Radiotracer was injected as a sharp pulse into the inlet p.peline. The pulse was monitored at the inlet and various points along the outlet pipeline using collimated scintillation detector. The peak to peak and total count methods were applied for radiotracer techniques and showed the comparable results with conventional flow meter.
A study to assess the concentration of radionuclides in spent resins of the PUSPATI TRIGA Mark II reactor coolant purification system has been carried out. Fresh spent resins collected and analysed in May 2010, after the changing of leaked heat exchanger in Sept. 2009 was found to contain 24Na, 122Sb, 51Cr, 124Sb, 58Co, 65Zn, 54Mn and 60Co. Old spent resins removed in 2001 and 2002 but analysed in 2010 indicated the presence of 60Co and 152Eu as radionuclides with half-lives of < 1 year might have already been decayed out. These results can be used to establish radionuclide inventory of the spent resins as part of radiation protection programme.
One of the most prevailing issues in the operation of Nuclear Reactor is the safety of the system. Worldwide publicity on a few nuclear accidents as well as the notorious Hiroshima and Nagasaki bombing have always brought about public fear on anything related to nuclear. Most findings on the nuclear reactor accidents are closely related to the reactor cooling system. Thus, the understanding of the behaviour of reactor cooling system is very important to ensure the development and improvement on safety can be continuously done. Throughout the development of nuclear reactor technology, investigation and analysis on reactor safety have gone through several phases. In the early days, analytical and experimental methods were employed. For the last three decades ID system level codes were widely used. The continuous development of nuclear reactor technology has brought about more complex system and processes of nuclear reactor operation. More detailed dimensional simulation codes are needed to assess these new reactors. This paper discusses the development of 3D CFD usage in nuclear reactor safety analysis worldwide. A brief review on the usage of CFD at Malaysia's Reactor TRIGA PUSPATI is also presented.
An appraisal of the regional reconnaissance geophysical, geochemical and geological data obtained under the Central Belt Project in 1977 – 1978 appeared to constitute favourable uranium exploration targets. Follow-up surveys conducted until the year 1990 have proposed the exploration area to be divided into three transects. Transect 1 covers the western part of the state of Kelantan, northwest Pahang and the eastern half of Perak. Transect 2 covers southeastern tip of Perak, west Pahang, eastern half of Wilayah Persekutuan, eastern portion of Selangor, and the northwest portion of Negeri Sembilan. Transect 3 covers central Kelantan, northwestern of Terengganu and northern portion of Pahang. Results of the study indicate that the Main Range, Bujang Melaka, and Bukit Tinggi Plutons are most fertile with uranium spectrometric rock values range from 13 to 25 ppm. Further investigations to zero down the target areas for uranium mineralization are strongly recommended over these areas.
Qualitative and quantitative analysis of samples require good judgment from the analysts. These two aspects in gamma spectrometric analysis of Proficiency Test and solid radioactive waste samples for the determination of radionuclides are discussed. It is vital to judge and decide what energy peaks belong to which radionuclides prior to the creation of customized radionuclide library for the analysis of specific samples. Corrections due to radionuclide decay and growth, and the half-life assigned to a particular radionuclide in the uranium and thorium series are also discussed. Discussion on judgment to confirm the presence of thorium in food samples based on gamma spectrometry and neutron activation analysis is also provided.
Data transmission in field works especially that is related to industry, gas and chemical is paramount importance to ensure data accuracy and delivery time. A development of wireless detector system for remote data acquisition to be applied in conducting fieldwork in industry is described in this paper. A wireless communication which is applied in the project development is a viable and cost-effective method of transmitting data from the detector to the laptop on the site to facilitate data storage and analysis automatically, which can be used in various applications such as column scanning. The project involves hardware design for the detector and electronics parts besides programming for control board and user interface. A prototype of a wireless gamma scintillation detector is developed with capabilities of transmitting data to computer via radio frequency (RF) and recording the data within the 433MHz band at baud rate of 19200.
Effect of washing solutions’ pH on removal of radium-226 from radium-contaminated soil using distilled water and humic acid extracted from Malaysian peat soil was studied by a single batch washing method. The study encompassed the extraction of humic acid and the washing of radium-contaminated soil using distilled water and humic acid solutions of varying pH in the range between 3 to 11. Activity of radium-226 was determined by gamma spectrometer. In the pH range studied, the removal of radium-226 was greater when humic acid solutions were used compared to distilled water. Greater removal of radium-226 was obtained using highly basic pH washing solutions compared to neutral and acidic solutions.
The Malaysian 1 MW TRIGA MARK II research reactor at Malaysian Nuclear Agency is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes for their use in agriculture, industry, and medicine. This study deals with the calculation of neutron flux and power distribution in PUSPATI TRIGA REACTOR (RTP) 14th core configuration. The 3-D continuous energy Monte Carlo code MCNP was used to develop a versatile and accurate full model of the TRIGA core and fuels. The model represents in detailed all components of the core with literally no physical approximation. Continuous energy cross-section data from the more recent nuclear data as well as S (α, β) thermal neutron scattering functions distributed with the MCNP code were used. Results of calculations are analyzed and discussed.
Mushroom can be used as a biological indicator in assessing radiological impact on the
environment. Radiological effect would be reflected through morphological changes as well as
those changes at molecular level. For this purpose, a preliminary work was conducted, which
included DNA isolation, optimization of PCR parameters for Inter-Simple Sequence Repeat (ISSR)
and primers screening on Pleurotus sajor caju mushroom strains from Nuclear Malaysia’s
Sterifeed Mushrooms Collection Centre. In this work, DNA isolation technique from cap and stalk
of fruit body were optimized and quantified. It was found that stalk produced highest amount of
genomic DNA at 304.01ng/µl and cap at 149.00ng/µl. A total of 100 ISSR primers were tested and
51 primers were successfully amplified. These primers will be used further for dose response
evaluation and molecular profiling in mushroom species.
“Batu Bersurat Terengganu (inscribed stone)” is the oldest artifact with Jawi writing on it. The
artifact proves that the Kingdom of Terengganu exist earlier than 1326 or 1386. To date, a lot of
studies on the content of the inscription have been carried out by historians and archaeologists, but
no scientific investigation about the material composition and its provenance has been performed.
This paper focuses on the study of the origin of the Batu Bersurat Terengganu using NeutronInduced
Prompt Gamma-Ray Techniques (NIPGAT). Portable NIPGAT system has been designed
and developed based on volumetric measurement methods and it will be considered as a nondestructive
testing. The system uses low activity of californium-252 (Cf-252) neutron radioactive
sources, gamma ray spectroscopy and special computer software to carry out the investigation. The
study found that the Batu Bersurat Terengganu is made of dolerite based on the elemental
composition of the stone. Although most of the scientific data for the study of the origin are already
obtained, but further research is still ongoing to complete the scope of this study.
This paper aims at presenting preliminary results of a survey on physical factors, namely tube
potential (kV), tube current exposure time product (mAs) and compressed breast thickness (CBT)
during voluntary mammography screening using Full-Field Digital Mammography (FFDM) System
in Malaysia. Retrospective data were collected from 1128 FFDM images of 282 women from three
major ethnic groups (Malay, Chinese and Indian) who underwent voluntary screening
mammography at Breast Centre, International Islamic University Malaysia from January to March
2008. Results from the present study were then compared with results from the previous study on
Screen-Film Mammography System (SFM) according to the ethnic group for both Cranio-caudal
(CC) and Mediol-Lateral (MLO) views. We found that the mean kV for CC view for the three ethnic
groups are Malay (28), Chinese (28) and Indian (28), and for MLO view are Malay (29), Chinese
(28) and Indian (29). These values are higher than the kV for SFM which were Malay (26), Chinese
(27) and Indian (26) for CC and Malay (26), Chinese (27) and Indian (26) for CC and MLO views
respectively. The mean mAs for CC and MLO views for FFDM were lower compared to SFM
systems. These values were Malay (104), Chinese (108) and Indian (91) for CC views and Malay
(106), Chinese (105), and Indian (94) for MLO views for the FFDM system. The values for SFM
system are for CC and MLO views were Malay (120), Chinese (106) and Indian (126), and Malay
(166), Chinese (132), Indian (183) respectively. The median CBT for CC and MLO views increased
by 27% and 7% respectively on the FFDM compared to the SFM system. In conclusion, the FFDM
operates with higher kV, lower mAs, and higher CBT when compared with SFM system. Median
CBT on CC and MLO view with FFDM system are 27% and 7% higher respectively compared to
the SFM. We are currently collecting data on mean glandular dose with FFDM systems to assess
how the change in local mammography practice influences this value. This will allow comparison
with related data from other parts of the world.
The acrylated palm oil (APO) nanoparticle is a potential product that can be used as carriers in
medical field. The main focus of the present study was to study the potential of the APO
nanoparticles for used in a controlled drug delivery system. The microemulsion system is used as a
medium to incorporate an active substance such as Thymoquinone (TQ) into the APO polymeric
micelle and then the radiation technique is used as a tool for the synthesis of TQ-loaded APO
nanoparticle. The nano-size TQ-loaded APO particles resulted the particle size of less than 150 nm
with spherical in shape. The TQ release profile was carried out in potassium buffer saline (PBS)
solutions (pH 7.4) at 37
oC. And, the zero-order model has been used to determine the mechanism
of the drug release from the corresponding nanoparticles, respectively. The TQ release was found
to be sustained and controlled in pH 7.4. At pH 7.4, the release of TQ followed the zero-order
model. The in-vitro drug release study showed a good prospect of the APO nanoparticle on being a
potential drug carrier as there are toxic against colon cancer cells and not toxic towards normal
cells. This suggested that the APO product produce using this radiation technique can be
developed into different type of carrier systems for controlled drug release applications.
Present of 241Am in the environment is being determined as part of surveillance and research
programs related to nuclear activities. The separation of 241Am from environmental samples was
carried out against the IAEA’s reference material by using an improved in-house radiochemical
separation method through anion exchange column, followed by the electro-deposition on a
stainless steel disc, and finally assayed on alpha spectrometry counting system. The resulting
spectra showed good isolated peak, indicating a good separation of the radionuclide of interest.
The analytical results were in good agreement with the certified value for IAEA-326 and IAEA-368
with the calculated U-score was 0.36 and 0.82, respectively, showing no significant difference
between the experimental and certified value. Using this method, distributions of 241Am in seabed
surface sediment in the Exclusive Economic Zone of East Coast Peninsular Malaysia were studied.
Samples were collected during June 2008 where the concentrations of 241Am were found to be
ranged from < 0.08 to 0.36 Bq/kg, dry weight.
An improved laboratory technique for measurement of polonium-210(
210Po) in environmental
samples has been developed in Radiochemistry and Environmental Laboratory (RAS), Malaysian
Nuclear Agency. To further improve this technique, a study with the objectives to determine the
optimum conditions for
210Po deposition and; evaluate the accuracy and precision results for
the determination of 2 1 0 P o in environmental samples was carried-out. Polonium-210 which
is an alpha emitter obtained in acidic solution through total digestion and dissolution of samples
has been efficiently plated onto one side of the silver disc in the spontaneous plating process for
measurement of its alpha activity. The optimum conditions for deposition of 210Po were achieved
using hydrochloric acid (HCl) media at acidity of 0.5 M with the presence of 1.0 gram hydroxyl
ammonium chloride and the plating temperature at 90
oC. The plating was carried out in 80 mL
HCl solution (0.5 M) for 4 hours. The recorded recoveries obtained using 2 0 9 P o tracers in
the CRM IAEA-385 and environmental samples were 85% – 98% whereby the efficiency of the
new technique is a distinct advantage over the existing techniques. Therefore, optimization of
deposition parameters is a prime importance to achieve accuracy and precision results as well as
economy and time saving
A study has been carried out using a gamma-ray spectrometric system to determine the natural
radioactivity level in bricks made from industrial waste and their associated radiation hazard.
Brick-1 and brick-2 contained waste from coal power plant and granite industry, respectively. The
leachability of radionuclides from these bricks was also investigated. The activity concentration
values of 226Ra,
228Ra,
232Th, and 40K are 64.25, 63.15, 67.9 and 254.19 Bq/kg, respectively in brick-
1, and 193, 164.48, 164.63 and 1348.75 Bq/kg, respectively in brick-2. The radiation hazard
indexes such as radium equivalent activities (Raeq), representative level index (Iγr), external hazard
index (Hex) and internal hazard index (Hin) were calculated and compared with the internationally
approved values. Results indicate that brick-1 showed less radiological hazard than brick-2. This
suggested that brick-1 could be used in building construction without exceeding the proposed
criterion level.The leachability of 226Ra for bricks showed the activity concentration slightly
exceeded 1 Bq/L which is the limit generally used for industrial wastewater.
Effects of 3 MeV electron (10 mA) irradiation at room temperature on the phase, microstructure,
electrical and life time properties of 4H-SiC wafer were investigated by scanning electron
microscopy (SEM), X-ray diffraction (XRD), four point probe current-voltage measurements and
positron annihilation spectroscopy. It was found that irradiation damage in SiC wafer is
significantly increased with the increase of radiation dose as observed in SEM. Irradiation also
resulted in modification of crystallite size as identified by XRD. The resistance of a sample before
irradiation was found to be 0.8 MΩ, whereas for a sample irradiated at 200 kGy, the resistance as
measured by four point probe was 5.2 MΩ. It seems that the increase of resistance hence, reduction
in conductivities could be due to defects induced by the radiation dose received then created
leakage currents at both reverse and low-forward biases and creation of traps in the SiC.
Meanwhile positron annihilation spectroscopy (PAS) was used to analyse the life time of irradiated
samples which nonetheless shows that all irradiated sample have similar life time of 151 ps. It was
observed that that no degradation process of materials experienced by SiC wafer irradiated at 500
kGy.
Development of biofertilizer seed treatments for okra seeds were carried out by mixing phosphate
solubilising bacteria (AP 3) and plant growth promoter (AP 2) with adhesives. The seeds were
coated with inoculums and four types of adhesives namely, Gum Arabic; Polyethylene Glycol
(PEG); Sodium Alginate and Methycellulose respectively. From eight seed treatments, all seed
treatments significantly increased seed germinations except treatment T4 (Gum Arabic and AP3).
In general, maximum germination rates and log of viable cells were observed when treated with
polyethylene glycol 4000 (PEG) mixed with AP2 (T7) and AP3 (T8). These results show that using
PEG as adhesive enhanced the germination rates and log of viable cells of AP2 and AP3. Thus,
PEG could be a good adhesive for seed treatment. In greenhouse experiment, okra seeds treatment
with AP2 and PEG (T1) showed the highest dry weight compared to other treatments. Seeds
treatment with AP3 and PEG (T2) showed higher contribution of N compare to seeds treatment
(T1). There were no significant different within seed treatments and urea treatment in okra yield.
All treatments significantly increased yields compared with control