The main component of most building materials in Malaysia is rocks. These rocks have been found to naturally contain U-238, Th-232 and K-40. In order to estimate the radiological impact to the dweller, the level of radionuclides present in various building materials available in Malaysia were analyzed using gamma spectrometry. The radiation hazard indexes were calculated based on the above results. The results showed that the activity concentration of natural radionuclides U-238, Th-232, K-40 were between 19.0 Bq/kg – 42.2 Bq/kg, 16.5 Bq/kg –28.8 Bq/kg and 243.3 Bq/kg – 614.2 Bq/kg respectively. On the whole the radionuclides concentrations were still below the global average of 50 Bq/kg, 50 Bq/kg and 500 Bq/kg for U-238, Th-232 and K-40 respectively. The radiation hazard indexes of the building materials were also lower than the maximum value suggested.
At present, soil and mineral based building material such as bricks are one of the main components in building construction in Malaysia. This building material is a direct source of radiation exposure since it contains naturally occurring radioactive materials (NORM). In this study, clay brick samples used were obtained from 7 factories in Selangor and Johore, Malaysia. The activity concentrations of 226 Ra, 232 Th and 40 K in these samples of clay bricks were determined using a comparative method and was analysed using gamma spectrometry with HPGe detector. The mean values of activity concentrations for 226 Ra, 232 Th and 40 K were found to be in the range of 39.04 ± 0.88 Bqkg-1 - 73.61 ± 5.32 Bqkg-1, 43.38 ± 2.60 Bqkg-1 - 73.45 ± 1.51 Bqkg-1, and 381.54 ± 11.39 Bqkg-1 - 699.63 ± 15.82 Bqkg-1, respectively. The radiation hazard of NORM in the samples was estimated by calculating the radium equivalent activity (Raeq), external hazard index (Hex) and internal hazard index (Hin). Radium equivalent activity (Raeq) determined was in the range of 151.90 Bqkg-1 - 194.22 Bqkg-1 which is lower than the limit of 370 Bqkg-1 (equivalent to 1.5 mSvyr-1 ) recommended in the NEA-OECD report in 1979, whereas external hazard index (Hex) and internal hazard index (Hin) were between 0.20 – 0.26 and 0.52 - 0.71 respectively. The annual effective dose rate exposure to a dweller received from the clay bricks was calculated to be in the range of 0.35 ± 0.18 mSvy-1 - 0.43 ± 0.09 mSvy-1.
Concentrations of Natural Occurring Radioactive Material (NORM) and terrestrial gamma radiation have been shown to be associated with certain lithology and soil types. An attempt was made to statistically predict and validate environmental gamma radiation dose rates based on limited number of actual field measurements using sodium iodide (NaI(Tl)) detector. Statistical analysis including the correlations between the actual and predicted dose were made based on 32 different lithology and soil type combinations. Results of field measurements, have shown that more than 50% of the predicted data were not significantly different from the actual measured data. The interpolation method in GIS was used to produce an isodose map based on the prediction equation. A correlation of multiple regression on the predicted versus lithology and soils dose rates gave relationships of DP = 0.35 DL + 0.82 DS – 0.02, r2 = 0.736. A predicted isodose map was subsequently plotted base on 4 dose rates classes, ranging from 0.1 – 0.3 μSvhr-1.
The concentrations of Naturally Occurring Radioactive Material (NORM) and their corresponding terrestrial gamma radiation have been shown to be associated with certain lithology and soil types. A possible relationships among gamma radiation levels, and the lithology and soil types make it possible to predict ionizing radiation level of an area that cannot be directly measured. A study was carried out to statistically predict and validate environmental gamma radiation dose rates based on actual field measurements using a sodium iodide detector. Results obtained showed that the predicted dose rate (Dp) may be determined using a multiple correlation regression equation, Dp = 0.35DL + 0.82 Ds – 0.02, that integrates dose rates contributed by different lithological structures (DL) and soil types (Ds). Statistical analysis on 32 different lithology and soil type combinations showed that more than 50% of the predicted data were not significantly different from the data measured in the field. A predicted isodose map was subsequently plotted base on 4 dose rate classes ranging from 0.1 – 0.3 μSv h-1.
Penggunaan bahan binaan yang mengandungi bahan radioaktif tabii (NORM) yang tinggi boleh meningkatkan kadar dos dedahan kepada penghuni di dalam sesebuah bangunan. Kebimbangan terhadap impak radiologi kepada penghuni menyebabkan perlunya dilakukan penilaian hazard radiologi yang berpunca daripada bahan binaan. Sehubungan itu, objektif kajian ini adalah untuk menentukan aras keradioaktifan tabii dalam bahan binaan di Malaysia serta menilai risiko radiologi yang diterima oleh penghuninya. Sebanyak 46 sampel pasir, 43 sampel kerikil dan 13 sampel simen Portland telah dianalisis menggunakan sistem spektrometri sinar gama. Hasil kajian mendapati kepekatan aktiviti bagi ketiga-tiga sampel bahan binaan berada pada julat 4.4 Bq kg-1 hingga 354.9 Bq kg-1, 2.4 Bq kg-1 hingga 263.9 Bq kg-1 dan 15.1 Bq kg-1 hingga 1931.7 Bq kg-1 bagi masing-masing 226Ra, 232Th dan 40K. Pengiraan kadar dos dedahan dalam bangunan mendapati semua sampel menghasilkan dos di bawah nilai 1500 μSv tahun-1, iaitu jumlah had dos yang disyorkan bagi bahan binaan. Hasil analisis ke atas nilai indeks aras perwakilan sinar gama, indeks hazard luaran dan indeks hazard dalaman mendapati sebahagian sampel memberikan bacaan melebihi nilai satu, iaitu had yang ditetapkan bagi bahan binaan. Penilaian risiko radiologi kepada penghuni dengan menggunakan kod komputer Resrad-Build mendapati kadar dos dedahan yang berpunca daripada simen Portland, pasir dan batu kerikil meningkat pada setiap tahun sepanjang tempoh 50 tahun.
Electricity has become one of the necessities for human daily activities. The presence of electric
current produces electromagnetic fields (EMF) at extremely low frequency (ELF). The problem arises
when scientists suggests a possible connection between ELF exposure to human health and safety.
Concerned about the safety and health of students and staff, Universiti Kebangsaan Malaysia (UKM)
took the initiative to identify possible ELF sources and measure their exposure in various locations
around the UKM main campus in Bangi. This paper reports the results obtained from the monitoring
of the magnetic flux density at three identified locations in the vicinity of the overhead high-voltage
transmission line which transverses the university compound and compare the maximum value results
with the exposure limit suggested by the International Committee on Non Ionising Radiation
Protection (ICNIRP) for ELF. Measurements were done with an (Extech) Three Axis
Electromagnetic Field (EMF) Meter (Model 430826) to determine the magnetic flux density. The
lateral profile method was applied as the standard measurement methodology. Results showed that the
maximum value of the magnetic flux density was 12.5 mG, which is below the suggested ICNIRP
public exposure limit of 1000 mG, or in percentage ratio, 1.25% of ICNIRP public exposure limit.
Results from the statistical Kruskal-Wallis test showed that there is a significant difference in the
distributions of the magnetic flux densities at the different locations (P < 0.05). In conclusion, the
measured locations are still safe for people in short-term exposure. However, long-term exposure
measurements still need to be done to provide concrete data on the ELF-emission levels in UKM.
Monazit merupakan mineral fosfat yang mengandungi unsur nadir bumi, torium dan uranium dalam kepekatan tertentu.
Kepekatan torium dalam monazit di Malaysia dilaporkan sekitar 2,525.0 - 40,868 ppm dan berpotensi digunakan
sebagai bahan api untuk kegunaan reaktor nuklear torium. Sehubungan dengan itu, kajian ini bertujuan mengkaji
proses pengekstrakan dan penulenan torium oksida (ThO2
) daripada monazit tempatan. Proses pengekstrakan dan
penulenan ThO2
dibahagikan kepada empat peringkat iaitu proses penghadaman, pengasingan, pengekstrakan pelarut
dan pengkalsinan. Pencirian sampel telah dilakukan melalui analisis spektrometri jisim gandingan plasma teraruh (ICPMS), analisis termogravimetri (TGA), pembelauan sinar-X (XRD) dan mikroskopi pengimbas elektron dengan spektroskopi
serakan tenaga sinar-X (SEM-EDS). Proses penghadaman telah menghasilkan larutan larut lesap monazit ((Th,REE,U)
(SO4
)
2
) yang mengandungi sehingga 99.77 ± 7.84 mg torium. Unsur nadir bumi (La, Ce, Nd, Pr, Sm, Eu dan Gd) telah
diasingkan daripada torium pada peratusan 96.73%. Manakala larutan Th(NO3
)
4
dan ThO2
yang dihasilkan masing- masing
berketulenan 97.10 ± 0.74% dan 98.85 ± 0.69%. Sehubungan dengan itu, kajian ini menunjukkan bahawa pengekstrakan
dan penulenan ThO2
daripada monazit tempatan boleh dilakukan melalui proses pengekstrakan berperingkat.