mohamad aminudin said

@moh.gov.my

Nuclear Medicine Physicists
INSTITUT KANSER NEGARA



           

https://researchid.co/aminhpj

RESEARCH, TEACHING, or OTHER INTERESTS

Radiation, Instrumentation

15

Scopus Publications

Scopus Publications

  • Performance evaluation of Gallium-68 radiopharmaceuticals production using liquid target PETtrace 800 cyclotron
    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

  • QUANTIFICATION OF ABSORBED DOSE IN<sup>90</sup>Y SELECTIVE INTERNAL RADIATION THERAPY FOR HEPATOCELLULAR CARCINOMA TREATMENT: A REVIEW
    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.

  • Does Single Computed Tomography Attenuation Correction able to Surrogate Serial Computed Tomography Attenuation Correction in Single-Photon Emission Computed Therapy Imaging for Peptide Receptor Radionuclide Therapy Dosimetry Result?
    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.

  • Evaluation of butterworth post-filtering effects on contrast and signal noise to ratio values for SPECT images reconstruction
    Dyg Masury Ahmad Saib, Nurul Zahirah Noor Azman, Mohd Aminudin Said, Muhd Izzat Muhd Aseri, Hana Mohammed Almarri, and Ramzun Maizan Ramli

    Elsevier BV

  • Optimization of scanning time of18f-fdg whole body pet/ct imaging in obese patients using quadratic dose protocol


  • The comparison of serial spect-ct imaging to estimate absorbed dose to the organ at risk from peptide receptor radionuclide therapy dosimetry


  • The quantification of PET–CT radiotracers to determine minimal scan time using quadratic formulation
    Mohamad Aminudin Said, Marianie Musarudin, and Nur Farahiyah Zulkaffli

    Springer Science and Business Media LLC

  • Quantitative imaging with commercial SPECT
    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.

  • Maximum standardized uptake value from quantitative bone single-photon emission computed tomography/computed tomography in differentiating metastatic and degenerative joint disease of the spine in prostate cancer patients
    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

  • Implementation of quadratic dose protocol for 18F-FDG whole-body PET imaging using a BGO-based PET/CT scanner, GE Discovery ST


  • I-124 pre-therapy dosimetry for the treatment of differentiated thyroid cancer: A single center experience


  • Lu-177 DOTATATE dosimetry for neuroendocrine tumor: Single center experience
    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.

  • The effective dose result of <sup>18</sup>F-FDG PET-CT paediatric patients
    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.

  • A simple low-cost of liquid I-131 dispenser for routine radiopharmaceutical dispensing at nuclear medicine department, Institut Kanser Negara
    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...

  • Assessment of radiation safety awareness among nuclear medicine nurses: A pilot study
    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.