@moh.gov.my
Nuclear Medicine Physicists
INSTITUT KANSER NEGARA
Radiation, Instrumentation
Scopus Publications
P. Morthy, M. Musarudin, N.S. Ab Shukor, M.A. Said, D. Xianling, and M.I. Saripan
Elsevier BV
H. Murat, M.A.A. Zulkifli, M.A. Said, M. Awang Kechik, D. Tahir, and M.K. Abdul Karim
Elsevier BV
H. Murat, M.M.A. Kechik, M.T. Chew, I. Kamal, M.A. Said, and M.K.A. Karim
EDP Sciences
The advent of PET/CT examinations has revolutionized cancer treatment, offering greater precision in diagnosis. Nonetheless, the ionizing radiation exposure during the examination could cause radiation cancer risk. Hence, this study aimed to evaluate the radiation dose and radiation-induced risk associated of whole-body PET/CT examinations that includes the 18F-FDG radionuclides. For this retrospective study, 40 participants were studied, with 20 men and 20 women. The average age and weight of the participants were 53.77 ± 15.78 years and 66.59 ± 16.94 kg respectively, and they were administered 424.64 ± 121.19 MBq of 18F-FDG before the PET/CT commenced. The IDAC-Dose 2.1 program was employed to calculate the absorbed dose and effective dose in organs such as the bladder, brain, lung, kidneys, colon, red bone marrow (RBM), stomach, liver, and thyroid. In this study, polynomial regression was used to fit the Lifetime Attributable Risk (LAR) values derived from the BEIR VII phase II report. The effective dose from the 18F-FDG PET/CT examination was 20.1 ± 7.9 mSv, with a ratio of E to the administered activity of 1.612 × 10−2 mSv/MBq, in accordance with ICRP standards. The related risk of cancer in the second part of the work did not include CT component. The estimated average cancer incidence from the PET alone was 7 and 8 cases per 100,000 persons exposed to 0.1Gy for men and women respectively, with PET-related effective doses ranging between 3.2 mSv to 27.3 mSv. In summary, the risk of cancer associated with current whole-body 18F-FDG PET/CT examinations is low, but it is essential to mitigate radiation exposure during these examinations and utilize suitable techniques to prevent stochastic effects from low-dose radiation exposure.
Zarif Ashhar, Muhammad Fakhrurazi Ahmad Fadzil, Zaitulhusna Md Safee, Firdaus Aziz, Ummi Habibah Ibarhim, Nik Muhammad Fitri Nik Afinde, Noratikah Mat Ail, Muhammad Ali Hazizi Jamal Harizan, Dzulieza Halib, Arieffuddin Alek Amran,et al.
Elsevier BV
Nurul Firzanah Baharuddin, Noorfatin Aida Baharul Amin, Noushin Anan, Kamran Hameed,, Mahayuddin Abdul Manap, Mohamad Aminudin Said, Nor Salita Ali, Dhalisa Hussin, Hazlin Hashim,et al.
Univ. of Malaya
Selective internal radiation therapy (SIRT) has emerged as a viable strategy for the treatment of incurable hepatic cancers. Although SIRT is a well-known therapy, continuous improvement in personalised dosimetry is required to improve the treatment planning and delivery of therapy. The ability to precisely foresee, plan, and administer the ideal dose to the tumour and non-tumoral tissues, including a final validation of the dose distribution, is the primary principle of radiation. The main way for safely personalised therapy for a maximum response while respecting normal tissue tolerances is to know the true absorbed dose to tissue compartments. Recent clinical studies highlighted the significance of personalised dosimetry to make it safer and more effective. Quantification of the absorbed dose distribution is of utmost importance in SIRT 90Y to optimise the hepatocellular carcinoma (HCC) treatment. The aim of this article was to review various dosimetric approaches in quantifying the absorbed dose of tumours and healthy liver tissue in 90Y SIRT. This article also compares the capabilities of organ-level dosimetry, voxel-level dosimetry and Monte Carlo simulation in assessing the absorbed dose in organs especially liver. The quantification of absorbed dose influences 90Y SIRT tumour dosimetry, while healthy liver absorbed dose values were comparable for all investigated imaging data. Personalised dosimetry for the tumour and healthy liver parenchyma after 90Y SIRT is recommended for patient-tailored therapy with enhanced therapeutic outcomes and for the safe administration of additional treatment cycles.
Mohamad Aminudin Bin Said, Hairil Rashmizal Abdul Razak, and Marianie Bnti Musarudin
Medknow
Peptide Receptor Radionuclide Therapy (PRRT) is the administration of a radionuclide, such as the Lu-177 label, along with a pharmaceutical agent to destroy the lesion cell. The first cycle of Lu-177 DOTA-TATE is an excellent way to estimate radionuclide uptake for organs at risk. To estimate the absorbed dose for a kidney, serial SPECT-CT imaging with up to five sets is required. In general, serial CT on patients would result in additional external exposure and extra time consuming, especially for low dose CT such as cone beam CT technology. However, by introducing a new method, such as optimized single CT (24 h) to perform with serial SPECT attenuation correction, additional external exposure from serial CT exposure could be reduced. Aims: The purpose of this study is to assess the agreement between single CT scanning as CT attenuation Correction with serial CT scanning for serial SPECT imaging as well as estimated absorbed dose to the organ at risk. Settings and Design: During the first cycle of Lu177-DOTA-TATE, all patients should undergo internal dosimetry technique using SPECT-CT imaging with a PHILIP Brightview XCT gamma camera. The quantifications of SPECT images are being used to measure the uptake activity to the organ. In this investigation, Partik's categorical grading criteria are being used to convert the numeric value of Lin's concordance coefficient into an ordinal scale. Method: Total of 9 patients at our institution was administered with Lu177-DOTA-TATE enroll in this study. SPECT-CT data were acquired using automatic body contouring with a total of 48 angular views at steps of 6° (15 s/projections). The pixel size is 4.66 x 4.66 x 4.66 mm, the images size set to one, and SPECT data has been acquired for three-bed positions extending from the abdomen to the thorax region. Low-dose CT imaging performed at an X-ray tube voltage of 120 kVp. Results: Our current result demonstrated by single CT scanning for SPECT attenuation shown the excellent agreement with standard serial CT imaging for organs at risk such as kidney 0.999, spleen 0.9951, liver 0.9951 and bladder 0.9972. Conclusions: When compared to the previous method, patients benefit significantly more from this study, such as lower CT exposure.
Dyg Masury Ahmad Saib, Nurul Zahirah Noor Azman, Mohd Aminudin Said, Muhd Izzat Muhd Aseri, Hana Mohammed Almarri, and Ramzun Maizan Ramli
Elsevier BV
Mohamad Aminudin Said, Marianie Musarudin, and Nur Farahiyah Zulkaffli
Springer Science and Business Media LLC
M A Said, M A Masud, and Abdul Razak H R
IOP Publishing
Abstract With the introduction of the Computed Tomography (CT) into the SPECT technology, SPECT-CT is now capable to quantify the uptake to the organ by the introduction of Activity Calibration Factor (ACF). We implemented three different phantoms geometry to obtain the ACF. First acquisition done with uniform cylinder phantom from Data Spectrum, followed with uniform NEMA IEC Body and uniform glass bottle allows the simulation of different type of clinical imaging study. Acquisitions were performed on a Brightview XCT (Philip) gamma camera. All acquisition and reconstruction protocol according to the clinical practice setting with different voxel volume sizes of 0.811 cm3, 0.104 cm3 and 0.012 cm3 to demonstrate the different values of ACFs. The ACFs for Tc-99m, I-131 and Lu-177 calculated from 3D segmentation of SPECT-CT images for scaling three different matrix sizes. The results obtained in this study demonstrated that SPECT-CT is able to quantify uptake at the organ, and it has high possibility to be used as quantitative SPECT in clinical practice in the future.
Mohd Fazrin Mohd Rohani, Norazlina Mat Nawi, Syed Ejaz Shamim, Wan Fatihah Wan Sohaimi, Wan Mohd Nazlee Wan Zainon, Marianie Musarudin, Mohamad Aminudin Said, and Hazlin Hashim
Springer Science and Business Media LLC
MA Said, MA Masud, MZ Zaini, RA Salleh, BN Lee, and R Zainon
IOP Publishing
Lu-177 labelled with DOTATE is widely acceptable to treat Neuroendocrine Tumor (NET) disease and it better improvement of quality of patients’ life since few years ago. However, the radionuclide toxicity becomes the main limitation of the (NET) treatment. Therefore, we performed a pilot study aimed to estimate radiation absorbed doses to dose-limiting organs to develop a systemic therapy with Lu-177 in NET patients. In this study, five set of planar whole body images was acquired every 0.5 hour, 4 hours, 24 hours, 48 hours and 72 hours after Lu-177 administrations. The planar image acquisition was done using Philip Brightview X with Medium Energy General Purpose Collimator (MEGP) collimator. All patients’ images in Conjugate View (CV) format were transferred into PMOD 3.7 Software for Region of Interest (ROI) analysis. The ROI were drawn at selected organs such as kidneys, liver, spleen and bladder. This study found that the mean absorbed dose for kidneys 0.62 ± 0.26 Gy/GBq, liver 0.63 ± 0.28 Gy/GBq, spleen 0.83 ± 0.73 Gy/GBq and bladder 0.14 ± 0.07 Gy/GBq. The radionuclide kinetic for the whole body 99.7 ± 0.1 percent at 0.5 hours, 79.5 ± 10.7 percent at 4 hours, 56.6 ± 10.3 percent at 24 hours, 43.2 ± 7.9 percent at 48 hours and 37.1 ± 9.0 percent at 72 hours. This study verifies that this planar quantitative method able to determine organ at risk and the result line with other published data.
D Hussin, M A Said, N S Ali, A A Tajuddin, and R Zainon
IOP Publishing
Paediatric patient received high exposure from both CT and PET examination. Automatic Exposure Control (AEC) is important in CT dose reduction. This study aimed to compare the effective dose obtained from PET-CT scanner with and without the use of AEC function. In this study, 68 patients underwent PET-CT examination without the use of AEC function, while 25 patients used the AEC function during the examination. Patients involved in this study were between 2 to 15 years old with varies of malignancies and epilepsy diseases. The effective dose obtained from PET and CT examinations was calculated based on recommendation from International Commission on Radiological Protection (ICRP) Publication 106 and ICRP publication 102. The outcome of this study shows that the radiation dose was reduced up to 20% with the use of AEC function. The mean average of effective dose result obtained from PET and CT examinations without the use of AEC and AEC function were found to be as 6.67 mSv, 6.77 mSv, 6.03mSv and 4.96 mSv respectively. Where total effective dose result of PET-CT with non-AEC and AEC were found to be 13.44 mSv and 10.99 mSv respectively. Conclusion of this study is, the installation of AEC function in PET-CT machine does play important role in CT dose reduction especially for paediatric patient.
M. A. Said, Z. N. Ashhar, N. E. F. Suhaimi, and R. Zainon
AIP Publishing LLC
In routine radiopharmaceutical Iodine-131 (131I) dispensing, the amount of radiation dose received by the personnel depends on the distance between the personnel and the source, the time spent manipulating the source and the amount of shielding used to reduce the dose rate from the source. The novel iRAD-I131 dispenser using recycle 131I liquid lead pot will lead into low cost production, less maintenance and low dose received by the personnel that prepared the 131I. The new fabricated of low cost 131I dispenser was tested and the dose received by personnel were evaluated. The body of lead material is made from 2.5 cm lead shielded coated with epoxy paint to absorb the radiation dose up to 7.4 GBq of 131 I. The lead pot was supported with two stainless steel rod. The Optically Stimulated Luminescence (OSL) nanodot was used in this study to measure the dose rate at both extremities for every personnel who prepared the 131I. Each OSL nanodot was attached at the fingertip. Three different personnel (experien...
N A Yunus, M H R O Abdullah, M A Said, and P E Ch'ng
IOP Publishing
All nuclear medicine nurses need to have some knowledge and awareness on radiation safety. At present, there is no study to address this issue in Malaysia. The aims of this study were (1) to determine the level of knowledge and awareness on radiation safety among nuclear medicine nurses at Putrajaya Hospital in Malaysia and (2) to assess the effectiveness of a training program provided by the hospital to increase the knowledge and awareness of the nuclear medicine nurses. A total of 27 respondents attending a training program on radiation safety were asked to complete a questionnaire. The questionnaire consists 16 items and were categorized into two main areas, namely general radiation knowledge and radiation safety. Survey data were collected before and after the training and were analyzed using descriptive statistics and paired sample t-test. Respondents were scored out of a total of 16 marks with 8 marks for each area. The findings showed that the range of total scores obtained by the nuclear medicine nurses before and after the training were 6-14 (with a mean score of 11.19) and 13-16 marks (with a mean score of 14.85), respectively. Findings also revealed that the mean score for the area of general radiation knowledge (7.59) was higher than that of the radiation safety (7.26). Currently, the knowledge and awareness on radiation safety among the nuclear medicine nurses are at the moderate level. It is recommended that a national study be conducted to assess and increase the level of knowledge and awareness among all nuclear medicine nurses in Malaysia.