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Nuclear Malaysia Secondary Standard Dosimetry Laboratory (SSDL) has been established since 1980 and is a member of the International Atomic Energy Agency (IAEA) / World Health Organization (WHO) Network of SSDL. In 2005, the SSDL became a member of the Asia Pacific Metrology Program (APMP). The main objective of its establishment is to improve dosimetric accuracy in various fields of radiation dosimetry. It maintains national standards for X-ray air kerma and absorbed dose for gamma and beta radiations. Its main facilities include a Cobalt-60 teletheraphy unit, a self-contained Cobalt-60 gamma irradiator, a constant potential X-ray system with a 320Kv tube, gamma calibrators and panoramic gamma irradiators with various activities of Caesium-137 and Cobalt-60 sources, secondary standard beta sources and an Americium-241/Be neutron calibrator. The main services offered by the SSDL are:
Calibration of Radiation Measuring Instruments
Calibration of radiation measuring instrument is legally required under the Radiation Protection (Basic Safety Standards) Regulations 1988. SSDL is the national centre for the calibration of radiation measuring instruments i.e. dosimeters used in radiotherapy and radiation survey meters for radiation protection. Four irradiation rooms are available to accommodate Personal and Area Dosimetry
Personal and area dosimetry are legally required under the Radiation Protection (Basic Safety Standards) Regulations 1988. The main purpose of personal dosimetry is to determine the dose received by radiation workers and to provide personal dose records. SSDL serve as a centre in providing personal and area dosimetry services to radiation workers in country. Types of High Dose Dosimetry for Industrial Application Radiation processing technology involves high-absorbed dose in the range between 0.1 and hundreds of kilogray (kGy). SSDL provides ceric-cerous and ferrous sulphate (Fricke) dosimeters for process control and quality assurance in radiation processing, utilising Cobalt-60 gamma irradiators. The radiation dose measured by ceric-cerous dosimeters can be evaluated using a simple equipment such as the electrochemical potentiometer cell. The evaluated dose is a guideline as regard to the amount of radiation exposed to the public. |