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সর্ব-শেষ হাল-নাগাদ: ৩০ জুলাই ২০১৫

স্বাস্থ্য পদার্থ ও তেজস্ক্রিয় বর্জ্য ব্যবস্থাপনা ইউনিট

 


Objectives

  • To ensure protection of man and the environment, at present & in future, from hazards & deleterious
  • effects of ionizing radiations associated with Radioactive Wastes (RW) and Radiation Sources (RS).
  • Carry out Scientific and engineering research to help develop safe and environmentally sound options
  • for dealing with certain low and intermediate – level radioactive waste
  • Maintain an inventory of radioactive waste in Bangladesh.
  • To achieve the objective, the laboratory has been conducting the following activities:
  • Assessment and control of radiation exposure to occupational workers & the public, by environmental radioactivity monitoring (ERM)
  • External & internal radiation dosimetry including quality assurance (QA)
  • Safe management of RW&RS including their ultimate disposal
  • Radiation protection services, etc.

 

Groups

  • Health Physics
  • Waste Management
  • Dosimetry

Activities

  • ERM Programme & Activities

    The programme and activities, including relevant radiation protection services, being conducted (on-site & off-site at ~ 10 km radial distances around AERE campus), aiming at assessment and control of radiation exposure to occupational workers and the public (both in normal and abnormal conditions of operations of the AERE nuclear facilities), are as follows:

    • Pre-and post operational monitoring of air, water, soil, grass and food samples for defining appropriate safety limits & code of practices
    • Area and personnel radiation monitoring services
    • Routine radiation survey in and around the nuclear facilities (RR, RIPLs, Neutron Generator, 60Co Irradiators, etc)
    • Collection of meteorological and demographic data.
  • RWM Programme & Activities
    • Safe collection and interim-storage of RWs/RS, including related services, are conducted as follows:
    • Solid & liquid RWs are collected, segregated at the point of generation and stored in interim-storage
    • rooms located within AERE, Nuclear Medicine Centres (NMCs), Institute of Nuclear Medicine (INM)
    • & other waste producers, premises;
    • Some of the RWS and SRS are collected and safely stored in on – site temporary storage room
    • (users’s premises), while all others are safely transported and stored in interim-storage rooms of CWPSF
    • within AERE campus.
    • Short – lived, low-level solid and liquid wastes are stored for delay decay, while all others are awaiting
    • further management e.g.,sorting, compaction, treatment, conditioning and interim-storage.
    • Gaseous effluents (mainly 41Ar) from RR are monitored and discharged, through the stack, to the
    • environment following ICRP limit.
    • Radiation monitoring services related with collection, segregation, packaging transfer/transportation
    • and temporary or interim-storage of RWs, RS
  • Management of Spent/Disused 226Ra –sources (under IAEA Model Project INT/4/131)

    About 1gm (Activity: 1Curie) of country’s known 226Ra sources (needles, applicators, calibration sources) was collected, after transported to AERE, encapsulated in Stainless steel, placed in lead shielding devices which has finally been placed in cement pre-fabricated MS drums (200L) and was safely temporarily stored within AERE (2000), later on, these conditioned Radium sources have been shifted and safely stored in the CWPSF, AERE.

  • Inventory of Radioactive Waste

    Nationwide inventory of radiation sources and radioactive wastes (including 226Ra) was initiated. The generation (RWs, SRS) is a continuous process; therefore countrywide inventory is updated from time to time.

  • Establishment of a semi –pilot scale Central Radioactive Waste Processing and Storage Facility

    The CWPSF has been implemented under Annual Development Programme of the country (1997 – 2004). The facility is intended to serve as a semi-pilot scale infrastructure for safe pre-disposal management of radioactive waste including SRS.

  • Radiation Dosimetry Programme and Activities
    • Calibration & standardization of radiation monitoring devices used in health sectors, research, industry, agriculture
    • To improve & ensure accuracy of output-dose measurements in teletherapy (137Cs,60Co) deep-therapy X-ray and Linear Accelerators (LINACS)
    • QA services in teletherapy, deep-therapy & diagnostic X-rays, fluoroscopy, medical LINACS.
    • Participation in the IAEA TLD intercomparison programme (International Quality Assurance Programme )
    • External monitoring by TLD
    • Internal monitoring by Whole body Counting (WBC)
  • Ongoing Project activities
    • IAEA TC Project on Strengthening of Central Waste Processing and Storage Facility and site Investigation for near surface disposal facility (BGD/3/006) (Counterpart: Dr. S.Ghose)
    • RCA Project on Strengthening Infrastructure for Radioactive Waste Management (BGD/3/009) (Counterpart: Dr. S.Ghose)
    • ADP Project on Strengthening of Secondary Standard Dosimetry Laboratory Facilities (Project Director : Mr. A. Koddus)
    • FNCA project on Radioactive Waste Management (Counterpart: Dr. M.Moinul Islam)
  • R & D Activities
    • Liquid wastes containing 134Cs, 137Cs, 60Co etc. are being studied by chemical precipitation and ion- Exchange-cum-membrane filtration methods.
    • Safe disposal of biological radioactive wastes (rat samples) exposed to 99m Tc in the AERE campus.
    • Pre operational safety analysis report was prepared on the establishment of a CWPSF, AERE, Savar, as per requirement of Nuclear Safety Radiation Control rules 1997 and IAEA.
    • Environmental Impact Assessment report was prepared on the basis of the existing data available in
    • AERE. The following parameters were considered: geography, geology, hydrology, meteorology, seismology, transportation and communication, demography, industrial installations, and facilities in the vicinity, to prepare the EIA.
    • Geo-scientific investigation covering a 25 km region around the AERE campus for site selection for establishing a pilot-scale near-surface repository for short-lived LILW within AERE (by 2010) is in progress.
    • Contaminated imported milk powder was disposed in an experimental-cum-demonstration shallow-land disposal trench (6m × 4m × 1.3m) within AERE campus. Environmental samples (grass, soil, water) of the experimental site are being examined to see the migration (if any) of the radionuclide.
    • Removal of radio nuclides from low level radioactive waste using chemical treatment
    • Radiological impact assessment from the radionuclide in soil around 12km radial distance of TRIGA
    • MARK II research reactor Evaluation of environmental safety methodologies for the disposal of low-level radioactive waste.
    • Gamma ray attenuation study of soil, building materials, for gamma energy 200 keV to 2000keV
    • Distribution of radionuclide in different types of locally available fruit samples
  • Expert Mission/Meeting/Workshop
    • MEXT/NSRA experts Meeting on ‘Present Situation and Issues of Low and Intermediate Level Waste Storage Facility in Bangladesh’ was held in INST, AERE, January 17 – 18, 2006.
    • A one member expert mission has been implemented under pre-operational safety assessment of the CWPSF, March 24 – 28, 2007.
  • Academic Activities

    Research Work (Thesis), at the level of M.Sc., M.Phil, Ph.D in collaboration with different educational institutions (e.g., Universities – J.U., BUET, etc.), are being conducted.

  • Services

    This unit through the following programs and activities has been striving towards achieving the objective:

    The programme and activities, including relevant radiation protection services, being conducted (on-site & off-site at ~ 10 km radial distances around AERE campus), aiming at assessment and control of radiation exposure to occupational workers and the public (both in normal and abnormal conditions of operations of the AERE nuclear facilities), are as follows:

    • Pre-and post operational monitoring of air, water, soil, grass and food samples for defining appropriate safety limits & code of practices
    • Area and personnel radiation monitoring services
    • Routine radiation survey in and around the nuclear facilities (RR, RIPLs, Neutron Generator, 60Co Irradiators, etc)
    • Collection of meteorological and demographic data.
    • Safe collection and interim-storage of RWs/RS, including related services, are conducted as follows:
    • Solid & liquid RWs are collected, segregated at the point of generation and stored in interim-storage
    • rooms located within AERE, Nuclear Medicine Centres (NMCs), Institute of Nuclear Medicine (INM)
    • & other waste producers, premises;
    • Some of the RWS and SRS are collected and safely stored in on – site temporary storage room
    • (users’s premises), while all others are safely transported and stored in interim-storage rooms of CWPSF
    • within AERE campus.
    • Short – lived, low-level solid and liquid wastes are stored for delay decay, while all others are awaiting
    • further management e.g.,sorting, compaction, treatment, conditioning and interim-storage.
    • Gaseous effluents (mainly 41Ar) from RR are monitored and discharged, through the stack, to the
    • environment following ICRP limit.
    • Radiation monitoring services related with collection, segregation, packaging transfer/transportation
    • and temporary or interim-storage of RWs, RS

Achievements

Management of Spent/Disused 226Ra –sources (under IAEA Model Project INT/4/131). About 1gm (Activity: 1Curie) of country’s known 226Ra sources (needles, applicators, calibration sources) was collected, after transported to AERE, encapsulated in Stainless steel, placed in lead shielding devices which has finally been placed in cement pre-fabricated MS drums (200L) and was safely temporarily stored within AERE (2000), later on, these conditioned Radium sources have been shifted and safely stored in the CWPSF, AERE.

Inventory of Radioactive Waste

Nationwide inventory of radiation sources and radioactive wastes (including 226Ra) was initiated. The generation (RWs, SRS) is a continuous process; therefore countrywide inventory is updated from time to time.

Establishment of a semi –pilot scale Central Radioactive Waste Processing and Storage Facility

The CWPSF has been implemented under Annual Development Programme of the country (1997 – 2004). The facility is intended to serve as a semi-pilot scale infrastructure for safe pre-disposal management of radioactive waste including SRS.

  • Calibration & standardization of radiation monitoring devices used in health sectors, research, industry, agriculture
  • To improve & ensure accuracy of output-dose measurements in teletherapy (137Cs, 60Co) deep-therapy X-ray and Linear Accelerators (LINACS)
  • QA services in teletherapy, deep-therapy & diagnostic X-rays, fluoroscopy, medical LINACS.
  • Participation in the IAEA TLD intercomparison programme (International Quality Assurance Programme)
  • External monitoring by TLD
  • Internal monitoring by Whole body Counting (WBC)
  • Liquid wastes containing 134Cs, 137Cs, 60Co etc. are being studied by chemical precipitation and ion- Exchange-cum-membrane filtration methods.
  • Safe disposal of biological radioactive wastes (rat samples) exposed to 99m Tc in the AERE campus.
  • Pre operational safety analysis report was prepared on the establishment of a CWPSF, AERE, Savar, as per requirement of Nuclear Safety Radiation Control rules 1997 and IAEA.
  • Environmental Impact Assessment report was prepared on the basis of the existing data available in
  • AERE. The following parameters were considered: geography, geology, hydrology, meteorology, seismology, transportation and communication, demography, industrial installations, and facilities in the vicinity, to prepare the EIA.
  • Geo-scientific investigation covering a 25 km region around the AERE campus for site selection for establishing a pilot-scale near-surface repository for short-lived LILW within AERE (by 2010) is in progress.
  • Contaminated imported milk powder was disposed in an experimental-cum-demonstration shallow-land disposal trench (6m × 4m × 1.3m) within AERE campus. Environmental samples (grass, soil, water) of the experimental site are being examined to see the migration (if any) of the radionuclide.
  • Removal of radio nuclides from low level radioactive waste using chemical treatment
  • Radiological impact assessment from the radionuclide in soil around 12km radial distance of TRIGA MARK II research reactor Evaluation of environmental safety methodologies for the disposal of low-level radioactive waste.
  • Gamma ray attenuation study of soil, building materials, for gamma energy 200 keV to 2000keV
  • Distribution of radionuclide in different types of locally available fruit samples

Major Facilities

  • Radiation Protection
  • Safe Handling of Radiation Material and Radiation Sources
  • Collection andStorage of Radioactive Waste
  • Calibration og Radiation Meauring Equipment

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