CENTER FOR RESEARCH REACTOR (CRR)
Brief History of CRR
The sole nuclear reactor in Bangladesh is the TRIGA research reactor operated by the Bangladesh Atomic Energy Commission (BAEC). It can produce 3 MW of steady-state thermal power. On September 14, 1986, the reactor reached its initial criticality. The reactor has been employed in a variety of research and utilisation disciplines, including workforce development for the country's nuclear power program, Neutron Activation Analysis (NAA), Neutron Radiography (NR), Neutron Scattering (NS), experimental reactor safety research, teaching, and training. The Centre for Research Reactor (CRR) is in charge of the operation and maintenance of the reactor and its related equipment and systems, as well as guaranteeing the required level of safety as specified in the Safety Analysis Report (SAR). CRR is also in charge of preparing various Safeguards and Additional Protocol-related reports for AERE sites on a regular basis. The IAEA receives these reports through BAEC's Nuclear Safety, Security, and Safeguards Division (NSSSD) and International Affairs Division (IAD).
Brief History of CRR
The sole nuclear reactor in Bangladesh is the TRIGA research reactor operated by the Bangladesh Atomic Energy Commission (BAEC). It can produce 3 MW of steady-state thermal power. On September 14, 1986, the reactor reached its initial criticality. The reactor has been employed in a variety of research and utilisation disciplines, including workforce development for the country's nuclear power program, Neutron Activation Analysis (NAA), Neutron Radiography (NR), Neutron Scattering (NS), experimental reactor safety research, teaching, and training. The Centre for Research Reactor (CRR) is in charge of the operation and maintenance of the reactor and its related equipment and systems, as well as guaranteeing the required level of safety as specified in the Safety Analysis Report (SAR). CRR is also in charge of preparing various Safeguards and Additional Protocol-related reports for AERE sites on a regular basis. The IAEA receives these reports through BAEC's Nuclear Safety, Security, and Safeguards Division (NSSSD) and International Affairs Division (IAD).
Figure: BAEC TRIGA MARK -11 Research Reactor (BTRR)
The TRIGA Mark-II research reactor is a graphite-reflected, light water-cooled reactor with a steady-state power level of 3 MW (thermal) and a pulse power level of 852 MW. The reactor will be used for a variety of objectives, including training, teaching, radioisotope production, and various research and development operations in nuclear science and technology. The reactor was made critical at 50W on September 14, 1986, and commissioned in October 1986 at a steady-state power of 3MW. The reactor core is located near the bottom of the reactor tank. The reactor tank, which is housed within the reactor shield structure, is made of the aluminium alloy 6061-T6. The tank is 8.23m in length and 1.98m in diameter. The tank contains 24,865 litters of demineralised water. The reactor core contains 100 fuel components (including 5 fuel follower control rods and 2 instrumented fuel elements). The Uranium utilized in BTRR is 19.7% enriched. 1 control rod for an air follower, 18 graphite dummy elements, and 1 Am-Be neutron source (strength: 3 Ci). Boron Carbide is the neutron absorber employed in the BTRR (B4C). U-ZrH is the moderator used in the BTRR. The reactor core is shielded with graphite, lead, demineralized water, and heavy concrete.