Displaying publications 1 - 20 of 39 in total

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  1. Fulltext Assessment of supported radon in ground water from highland area using portable continuous radon monitor
    Ahmad Saat, Nor Shazlina Zainal, Zaini Hamzah
    Journal of Nuclear and Related Technologies, 2012;2012(2):22-33.
    MyJurnal
    Ground water contain natural radioactivity associated with uranium and thorium that present naturally in rocks and soils. Humans may be exposed to the emission of energetic alpha particle from supported radon decaying process in this water when it is inhaled or ingested. Assessment of supported radon in ground water was carried out using fourteen ground water samples from Cameron Highlands. The measurement was accomplished by degassing the water samples using pump and then allowing the gas to flow into specially constructed 0.0191 m8 metal chamber. The activity concentration of supported radon in water sample was measured using continuous radon monitor inside the radon chamber. Measurement was carried out at one hour interval for twenty four hours. The hourly supported radon concentration was found to stabilize after about 8 hours. The stabilized concentration was used to determine supported radon activity concentration in the water samples. Results of the study show that depending on the sampling location, the activity concentrations of supported radon are in the range from 0.09 - 0.48 Bq/L which is lower than the activity concentration of radon in drinking water as proposed by USEPA (11 Bq/L).
    Matched MeSH terms: Radioactivity
  2. Radiobiological long-term accumulation of environmental alpha radioactivity in extracted human teeth and animal bones in Malaysia
    Almayahi BA, Tajuddin AA, Jaafar MS
    J Environ Radioact, 2014 Mar;129:140-7.
    PMID: 24462923 DOI: 10.1016/j.jenvrad.2014.01.001
    In this study, the radiobiological analysis of natural alpha emitters in extracted human teeth and animal bones from Malaysia was estimated. The microdistributions of alpha particles in tooth and bone samples were measured using CR-39 alpha-particle track detectors. The lowest and highest alpha emission rates in teeth in the Kedah and Perak states were 0.0080 ± 0.0005 mBq cm(-2) and 0.061 ± 0.008 mBq cm(-2), whereas those of bones in the Perlis and Kedah states were 0.0140 ± 0.0001 mBq cm(-2) and 0.7700 ± 0.0282 mBq cm(-2), respectively. The average alpha emission rate in male teeth was 0.0209 ± 0.0008 mBq cm(-2), whereas that of female teeth was 0.0199 ± 0.0010 mBq cm(-2). The alpha emission rate in teeth is higher in smokers (0.0228 ± 0.0008 mBq cm(-2)) than in non-smokers (0.0179 ± 0.0008 mBq cm(-2)). Such difference was found statistically significant (p < 0.01).
    Matched MeSH terms: Radioactivity
  3. Assessment of natural radioactivity levels in rocks and their relationships with the geological structure of Johor state, Malaysia
    Alnour IA, Wagiran H, Ibrahim N, Hamzah S, Elias MS, Laili Z, et al.
    Radiat Prot Dosimetry, 2014 Jan;158(2):201-7.
    PMID: 23965286 DOI: 10.1093/rpd/nct206
    The distribution of natural radionuclides ((238)U, (232)Th and (40)K) and their radiological hazard effect in rocks collected from the state of Johor, Malaysia were determined by gamma spectroscopy using a high-purity germanium detector. The highest values of (238)U, (232)Th and (40)K activity concentrations (67±6, 85±7 and 722±18 Bg kg(-1), respectively) were observed in the granite rock. The lowest concentrations of (238)U and (232)Th (2±0.1 Bq kg(-1) for (238)U and 2±0.1 Bq kg(-1) for (232)Th) were observed in gabbro rock. The lowest concentration of (40)K (45±2 Bq kg(-1)) was detected in sandstone. The radium equivalent activity concentrations for all rock samples investigated were lower than the internationally accepted value of 370 Bq kg(-1). The highest value of radium equivalent in the present study (239±17 Bq kg(-1)) was recorded in the area of granite belonging to an acid intrusive rock geological structure. The absorbed dose rate was found to range from 4 to 112 nGy h(-1). The effective dose ranged from 5 to 138 μSv h(-1). The internal and external hazard index values were given in results lower than unity. The purpose of this study is to provide information related to radioactivity background levels and the effects of radiation on residents in the study area under investigation. Moreover, the relationships between the radioactivity levels in the rocks within the geological structure of the studied area are discussed.
    Matched MeSH terms: Radioactivity
  4. Measurement of gross alpha and beta activity concentration in groundwater of Jordan: groundwater quality, annual effective dose and lifetime risk assessment
    Alomari AH, Saleh MA, Hashim S, Alsayaheen A, Abdeldin I, Bani Khalaf R
    J Water Health, 2019 Dec;17(6):957-970.
    PMID: 31850902 DOI: 10.2166/wh.2019.158
    The current study was conducted to measure the activity concentration of the gross alpha and beta in 87 groundwater samples collected from the productive aquifers that constitute a major source of groundwater to evaluate the annual effective dose and the corresponding health impact on the population and to investigate the quality of groundwater in Jordan. The mean activity concentration of gross alpha and beta in groundwater ranges from 0.26 ± 0.03 to 3.58 ± 0.55 Bq L-1 and from 0.51 ± 0.07 to 3.43 ± 0.46 Bq L-1, respectively. A very strong relationship was found between gross alpha and beta activity concentrations. The annual effective dose for alpha and beta was found in the range of 0.32-2.40 mSv with a mean value of 0.89 mSv, which is nine times higher than the World Health Organization (WHO) recommended limit and one and half times higher than the national regulation limit. The mean lifetime risk was found to be 45.47 × 10-4 higher than the Jordanian estimated upper-bound lifetime risk of 25 × 10-4. The data obtained in the study would be the baseline for further epidemiological studies on health effects related to the exposure to natural radioactivity in Jordan.
    Matched MeSH terms: Radioactivity*
  5. Assessment of Natural Radioactivity Levels and Radiation Hazards in Agricultural and Virgin Soil in the State of Kedah, North of Malaysia
    Alzubaidi G, Hamid FB, Abdul Rahman I
    ScientificWorldJournal, 2016;2016:6178103.
    PMID: 27965987
    The activity concentrations of naturally occurring radionuclides (226)Ra, (232)Th, and (40)K were determined in 30 agricultural and virgin soil samples randomly collected from Kedah, north of Malaysia, at a fertile soil depth of 0-30 cm. Gamma-ray spectrometry was applied using high-purity germanium (HPGe) gamma-ray detector and a PC-based MCA. The mean radioactivity concentrations of (226)Ra, (232)Th, and (40)K were found to be 102.08 ± 3.96, 133.96 ± 2.92, and 325.87 ± 9.83 Bq kg(-1), respectively, in agricultural soils and 65.24 ± 2.00, 83.39 ± 2.27, and 136.98 ± 9.76 Bq kg(-1), respectively, in virgin soils. The radioactivity concentrations in agricultural soils are higher than those in virgin soils and compared with those reported in other countries. The mean values of radium equivalent activity (Raeq), absorbed dose rates D (nGy h(-1)), annual effective dose equivalent, and external hazard index (Hex) are 458.785 Bq kg(-1), 141.62 nGy h(-1), and 0.169 mSv y(-1), respectively, in agricultural soils and 214.293 Bq kg(-1), 87.47 nGy h(-1), and 0.106 mSv y(-1), respectively, in virgin soils, with average Hex of 0.525. Results were discussed and compared with those reported in similar studies and with internationally recommended values.
    Matched MeSH terms: Radioactivity
  6. Radionuclide emissions from a coal-fired power plant
    Amin YM, Khandaker MU, Shyen AK, Mahat RH, Nor RM, Bradley DA
    Appl Radiat Isot, 2013 Oct;80:109-16.
    PMID: 23891979 DOI: 10.1016/j.apradiso.2013.06.014
    Current study concerns measurement of radioactivity levels in areas surrounding a 2420 MW thermal power plant fueled predominantly by bituminous coal. The concentrations of (226)Ra, (232)Th and (40)K in onsite bottom-ash were found to be 139 Bq/kg, 108 Bq/kg and 291 Bq/kg, respectively, the levels for these radiolnuclides in soil decreasing with distance from the power plant. At the plant perimeter the respective radionuclide concentrations were 87 Bq/kg, 74 Bq/kg and 297 Bq/kg. In a nearby town, the corresponding concentrations were 104 Bq/kg, 52 Bq/kg and 358 Bq/kg, suggestive of use of TENORM affected soils. The mean radium equivalent activities (Raeq) in soil and ash sample in the town were 205 Bq/kg and 316 Bq/kg, respectively. The Kapar plant ash/slag appears to contain a higher level of TENORM than the world average. The degree of contamination is much higher inside the town where slag has been mixed with topsoil as landfill or as simple domestic waste. For the prevailing levels of exposure and a worst case senario, the predicted committed effective dose due to ingestion and inhalation for intake durations of 1- and 30 years would be 4.2 μSv and 220 μSv, respectively.
    Matched MeSH terms: Radioactivity
  7. Radioactivity and heat production characterization by natural gamma ray well logging and multi-fractal techniques in banting district, Malaysia
    Asfahani J, Samuding K, Mostapa R, Othman O
    Appl Radiat Isot, 2021 Jan;167:109296.
    PMID: 33022484 DOI: 10.1016/j.apradiso.2020.109296
    Natural gamma ray well logging technique is used to characterize the radioactivity (GR) laterally and vertically in Banting district, SW of Malaysia. Seven drilled boreholes, along N-S profile with their natural gamma ray records are utilized to compute the heat production (HP) parameter, based on the Bucker and Rybach relationship.The analysis of 3467 measured points in those boreholes indicates that GR varies between 6.24 API and 358.4 API with an average of 79.95 API, while HP varies between 0.086 and 5.65 μw/m3 with an average of 1.25 μw/m3.The multi-fractal Concentration-Number (C-N) is used to characterize the radioactivity and heat production variations and to isolate different GR and HP populations in the study region. The high radioactivity and heat production ranges are mainly related to the silty clay layers, accompanied by uranium and thorium.
    Matched MeSH terms: Radioactivity
  8. Fulltext Radioactivity of 210Po in the environmental samples from Kapar, Malaysia
    Asnor Azrin Sabuti, Che Abd Rahim Mohamed, Zaharudin Ahmad
    Journal of Nuclear and Related Technologies, 2010;2010(1):29-39.
    MyJurnal
    Various environmental samples (seawater, TSS, sediment, rainwater and fly ash) from eight different stations near Kapar coastal area were analyzed. The 210 Po activity concentrations in liquid samples (seawater and rainwater) varied between 0.34 ± 0.03 mBq L-1 to 22.44 ± 0.53 mBq L-1 . Whereas the concentrations in particulate samples (TSS, sediment and fly ash) varied between 43.79 ± 2.31 Bqkg-1 to 364.48 ± 5.43 Bqkg-1 . Results also showed the radioactivity in Kapar coastal is higher than most of Malaysian coast, reaching a factor of seven. This condition is mainly due to the operation of a coal-fired power plant nearby. This study also clarify the variability of 210 Po in environment was strongly influenced from rainfall events especially during wet seasons.
    Matched MeSH terms: Radioactivity
  9. Fulltext Renal targeting potential of a polymeric drug carrier, poly-l-glutamic acid, in normal and diabetic rats
    Chai HJ, Kiew LV, Chin Y, Norazit A, Mohd Noor S, Lo YL, et al.
    Int J Nanomedicine, 2017;12:577-591.
    PMID: 28144140 DOI: 10.2147/IJN.S111284
    BACKGROUND AND PURPOSE: Poly-l-glutamic acid (PG) has been used widely as a carrier to deliver anticancer chemotherapeutics. This study evaluates PG as a selective renal drug carrier.

    EXPERIMENTAL APPROACH: 3H-deoxycytidine-labeled PGs (17 or 41 kDa) and 3H-deoxycytidine were administered intravenously to normal rats and streptozotocin-induced diabetic rats. The biodistribution of these compounds was determined over 24 h. Accumulation of PG in normal kidneys was also tracked using 5-(aminoacetamido) fluorescein (fluoresceinyl glycine amide)-labeled PG (PG-AF). To evaluate the potential of PGs in ferrying renal protective anti-oxidative stress compounds, the model drug 4-(2-aminoethyl)benzenesulfonyl fluoride hydrochloride (AEBSF) was conjugated to 41 kDa PG to form PG-AEBSF. PG-AEBSF was then characterized and evaluated for intracellular anti-oxidative stress efficacy (relative to free AEBSF).

    RESULTS: In the normal rat kidneys, 17 kDa radiolabeled PG (PG-Tr) presents a 7-fold higher, while 41 kDa PG-Tr shows a 15-fold higher renal accumulation than the free radiolabel after 24 h post injection. The accumulation of PG-AF was primarily found in the renal tubular tissues at 2 and 6 h after an intravenous administration. In the diabetic (oxidative stress-induced) kidneys, 41 kDa PG-Tr showed the greatest renal accumulation of 8-fold higher than the free compound 24 h post dose. Meanwhile, the synthesized PG-AEBSF was found to inhibit intracellular nicotinamide adenine dinucleotide phosphate oxidase (a reactive oxygen species generator) at an efficiency that is comparable to that of free AEBSF. This indicates the preservation of the anti-oxidative stress properties of AEBSF in the conjugated state.

    CONCLUSION/IMPLICATIONS: The favorable accumulation property of 41 kDa PG in normal and oxidative stress-induced kidneys, along with its capabilities in conserving the pharmacological properties of the conjugated renal protective drugs, supports its role as a potential renal targeting drug carrier.

    Matched MeSH terms: Radioactivity
  10. Fulltext Effect of A13+, Ca2+, Cu2+ and Fe2+ on removal of Radium-226 from Radium-Contaminated soil using humic acid
    Esther Phillip, Muhamat Omar, Muhamad Samudi Yasir, Mohd Zaidi Ibrahim, Zalina Laili
    Journal of Nuclear and Related Technologies, 2012;2012(2):7-13.
    MyJurnal
    Effect of AP+, Ca", Cu" and Fe" on the removal of radium-226 from radium-contaminated soil using humic acid extracted from a Malaysian peat soil was investigated using batch washing method. The concentration of Al,+ Ca", Cu" and Fe" ranged from 0 to 100 ppm. The radioactivity concentration of radium-226 was determined by gamma spectrometer. The removal of radium-226 was enhanced in the presence of AP' with concentration between 20 - 60 ppm. Meanwhile, higher concentration of 80 - 100 ppm did not lead to further increase in the removal of radium-226. The removal of radium-226 was decreased in the presence of Ca" and Cu". In the presence of Fe" with concentration between 20 - 60 ppm, decrease in the removal of radium-226 was also observed. Nevertheless, at concentration between 80 - 100 ppm, the presence of Fe" led to increase in the removal of radium-226.
    Matched MeSH terms: Radioactivity
  11. Fulltext Naturally Occurring Radioactive Materials in Bracelets and Necklaces: Radiological Risk Evaluation
    Hassan HJ, Hashim S, Abu Hanifah NZH, Ghoshal SK, Sanusi MSM, Binti Suhailin FH, et al.
    Int J Environ Res Public Health, 2021 10 24;18(21).
    PMID: 34769689 DOI: 10.3390/ijerph182111170
    A particular category of jewelry is one involving bracelets and necklaces that are deliberately made to contain naturally occurring radioactive material (NORM)-purveyors making unsubstantiated claims for health benefits from the release of negative ions. Conversely, within the bounds of the linear no-threshold model, long-term use presents a radiological risk to wearers. Evaluation is conducted herein of the radiological risk arising from wearing these products and gamma-ray spectrometry is used to determine the radioactivity levels and annual effective dose of 15 commercially available bracelets (samples B1 to B15) and five necklaces (samples N16 to N20). Various use scenarios are considered; a Geant4 Monte Carlo (Geant4 MC) simulation is also performed to validate the experimental results. The dose conversion coefficient for external radiation and skin equivalent doses were also evaluated. Among the necklaces, sample N16 showed the greatest levels of radioactivity, at 246 ± 35, 1682 ± 118, and 221 ± 40 Bq, for 238U, 232Th, and 40K, respectively. For the bracelets, for 238U and 232Th, sample B15 displayed the greatest level of radioactivity, at 146 ± 21 and 980 ± 71 Bq, respectively. N16 offered the greatest percentage concentrations of U and Th, with means of 0.073 ± 0.0002% and 1.51 ± 0.0015%, respectively, giving rise to an estimated annual effective dose exposure of 1.22 mSv, substantially in excess of the ICRP recommended limit of 1 mSv/year.
    Matched MeSH terms: Radioactivity*
  12. Fulltext In-situ compositional analysis and provenance study of the historic terengganu stone (the inscribed stone “Batu Bersurat”) using neutron-induced prompt gamma-ray techniques (NIPGAT)
    Jaafar Abdullah, Roslan Yahya, Lahasen@Norman Shah Dahing, Hearie Hassan, Engku Mohd Fahmi Engku Chik, Mohamad Rabaie Shari, et al.
    Jurnal Sains Nuklear Malaysia, 2013;25(2):9-19.
    MyJurnal
    “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.
    Matched MeSH terms: Radioactivity
  13. Fulltext Investigation of natural environmental radioactivity concentration in soil of coastaline area of Ado-Odo/Ota Nigeria and its radiological implications
    Joel ES, Maxwell O, Adewoyin OO, Olawole OC, Arijaje TE, Embong Z, et al.
    Sci Rep, 2019 03 12;9(1):4219.
    PMID: 30862825 DOI: 10.1038/s41598-019-40884-0
    Natural radioactivity in coastaline area soil of Ado-Odo/Ota has been carried out to ascertain the presence of radionuclides using gamma-ray spectroscopy (HPGe detector). The result showed that U-238, Th-232 and K-40 ranged from 24 ± 7-49 ± 10; 67 ± 6-120 ± 9 and 88 ± 17-139 ± 20 Bqkg-1 respectively. The radium equivalent for the samples ranged from 132.51 to 230.91 Bqkg-1 with mean value of 185.89 Bqkg-1. The mean value for the gamma dose rate for the soil samples was estimated to be 81.32 nGyh-1. The estimated values of annual effective dose equivalent ranged from 0.61 to 1.07 mSv y-1. The estimation of alpha index representative (Iα) ranged from 0.12 to 0.24 with mean value of 0.21 while the gamma representative index ranged between 0.465 and 0.810. The activity utilization index of the soil samples ranged from 1.09 to 1.89 with mean value of 1.53. The radiological implication in the study area has shown that the soil samples with gamma dose rate value of 89.99 nGyh-1, 94.39 nGyh-1, 97.40 nGyh-1 and 101.04 nGyh-1 respectively are higher than the recommended value of 80 nGyh-1 and may pose health implication for long term exposure.
    Matched MeSH terms: Radioactivity
  14. Fulltext Radiological impact assessment in disposal of treated sludge
    Khairuddin Mohamad Kontol, Ismail Sulaiman, Faizal Azrin Abdul Razalim
    Jurnal Sains Nuklear Malaysia, 2015;27(2):23-30.
    MyJurnal
    Sludge and scales produced during oil and gas production contain enhanced naturally occurring
    radioactive material (NORM). Sludge and scales are under the jurisdiction of Department of
    Environment (DOE) and also Atomic Energy Licensing Board (AELB). AELB has issued a
    guideline regarding the disposal of sludge and scales as in its guideline (LEM/TEK/30 SEM.2,
    1996). In this guideline, Radiological Impact Assessment (RIA) should be carried out on all
    proposed disposals and has to demonstrate that no member of public will be exposed to more than
    1 mSv/y. This paper presented RIA analysis using RESRAD computer code for the disposal of
    treated sludge. RESRAD (RESidual RADioactive) developed by Argonne National Laboratory is to
    estimate radiation doses and risks from residual radioactive materials. The dose received by the
    member of public is found to be well below the stipulated limit.
    Matched MeSH terms: Radioactivity
  15. Fulltext Role of total activity concentration in radiological impact assessment in the disposal of tenorm waste from oil and gas industry
    Khairuddin Mohamad Kontol, Ismail Sulaiman
    Jurnal Sains Nuklear Malaysia, 2017;29(1):13-17.
    MyJurnal
    A study to determine whether Radiological Impact Assessment (RIA) is needed for landfill disposal of treated sludge (slag) from oil and gas industries has been carried out. Radioactivity level of slag and soil samples have been measured using gamma spectrometry system and its Total Activity Concentration (TAC) has been calculated. It was found that TAC (inclusive background) was within the control limit set by the AELB i.e. 3 Bq/g as stipulated in LEM/TEK 58 (AELB, 2009). Therefore, as a result from this study, RIA is not required and the allocated area can be used for the landfill disposal of treated sludge (slag).
    Matched MeSH terms: Radioactivity
  16. Fulltext Level of naturally occurring radioactive material, K-40 in oil palm's cultivated soil
    Masitah Alias, Zaini Hamzah, Ahmad Saat, Muhamat Omar, Zakaria Tajuddin, W. Mohamad W.A. Kadir, et al.
    Journal of Nuclear and Related Technologies, 2004;2004(2):1-11.
    MyJurnal
    The existence of Naturally Occurring Radioactive Materials (NORM) such as K-40 was studied all over the world for their characteristics and effects on human and environment. K-40 exist in the earth crust with the concentration about 1.8 mg/kg or 481 Bq/g.. In this study, the level of K-40 in soil samples were measured using gamma spectrometer equipped with hyper pure germanium detector. The samples were collected from an oil palm cultivated area of Jengka 15, in Maran District, Pahang. The results show the level of K-40 activities at various locations. The activities of K-40 are in the range 52.9-150.5 Bq/kg and total potassium concentrations are 1.60-4.50%. There are no correlation between activities of K-40 with elevation i.e. R2= 0.0885.
    Matched MeSH terms: Radioactivity
  17. Fulltext Properties of concrete/boron carbide as neutron shielding materials
    Mohd Reusmaazran Yusof, Yusof Abdullah, Rusnah Mustaffa, Abdul Aziz Mohamed, Nurhaslinda Ee Abdullah, Fatin Nabilah Tajul Ariffin
    Journal of Nuclear and Related Technologies, 2011;2011(2):15-25.
    MyJurnal
    Cement and concrete has been widely used as shielding material in reactor nuclear in order to minimize exposure to individuals. In this paper we present boron based concrete as neutron shielding for nuclear reactor applications. Concrete specimens with dimension of 10x10x10 cm were used and irradiated with neutron radiation of 252-californium. Characterization of physical, mechanical and radiation attenuation properties of concrete were carried out. The results show that the shielding performance is better than ordinary concrete. From the result, we confirmed that the performance of the concrete/boron carbide is suitable for practical use.
    Matched MeSH terms: Radioactivity
  18. Fulltext A systematic approach in the gamma spectrometric determination of radionuclides in coolant of puspati triga reactor
    Muhamat Omar, Zalina Laili, Abd Khalik Wood, Julia Abdul Karim, Zarina Masood, Mohd Fazli Zakaria, et al.
    Jurnal Sains Nuklear Malaysia, 2011;23(2):1-11.
    MyJurnal
    A systematic study to assess the concentration of radionuclides in primary coolant and associated water samples from the operation of a TRIGA Mark II reactor has been carried out. The samples were transferred into appropriate counting container and were counted by efficiency-calibrated gamma spectrometer systems for several hours to obtain statistically adequate data for qualitative and quantitative evaluation of the radioactive materials presence. The primary coolant was found to contain various gamma emitting radionuclides including 24Na, 41Ar, 42K, 51Cr, , 54Mn, 56Mn, 60Co, 99mTc, 122Sb, 124Sb and 187W. Most of the detected radionuclides were inferred to be originated from activation products of (n,) nuclear reactions of elements of reactor components such as stainless steel and aluminium alloy used in the reactor system. The study confirms the integrity of the reactor system with no apparent release of any fission products radionuclide into the coolant water system.
    Matched MeSH terms: Radioactivity
  19. Fulltext Judgment on the presence of radionuclides in sample analysis: A case study
    Muhamat Omar, Zalina Laili, Mohd Suhaimi Hamzah
    Jurnal Sains Nuklear Malaysia, 2012;24(1):33-42.
    MyJurnal
    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.
    Matched MeSH terms: Radioactivity
  20. Fulltext Characterization of a gas-purge method to access 11C-carbondioxide radioactivity in blood
    Ng, Yen, Green Mark, A.
    Jurnal Sains Nuklear Malaysia, 2014;26(2):14-16.
    MyJurnal
    Carbon-11 labeled radiotracers, such as 11C-acetate and
    11C-palmitate are widely used in positron
    emission tomography (PET) for noninvasive evaluation of myocardial metabolism under varied
    physiological conditions.These tracers are attractive probes of tissue physiology, because they are
    simply radiolabled versions of the native biochemical substrates. One of the major metabolites
    generated by these tracers upon the administration is 11CO2 produced via the citric acid cycle. In
    quantitative modeling of
    11C-acetate and
    11C-palmitate PET data, the fraction of blood
    11C
    radioactivity present as
    11CO2 needs to be measured to obtain a correct radiotracer arterial
    input function. Accordingly, the literature describes a method whereby the total blood
    11C-activity
    is counted in blood samples treated with base solution, while the fraction of
    1 1CO2 is measured
    after the blood is treated with acid followed by a 10 minutes gas-purge. However, a detailed
    description of the experimental validation of this method was not provided. The goal of this study
    was to test the reliability of a 10 minute gas purging method used to assay
    11CO2 radioactivity in
    blood
    Matched MeSH terms: Radioactivity
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