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Plan for the safe decommissioning of the BAEC 3MW TRIGA MARK-II researchreactor

机译:计划对BAEC 3MW TRIGA MARK-II研究反应器进行安全退役

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The 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC) has been operating since September 14, 1986. The reactor is used for radioisotope production (131I, 99mTc, 46Sc), various R&D activities, and manpower training. The reactor has been operated successfully since it's commissioning with the exception of a few reportable incidents. Of these, the decay tank leakage incident of 1997 is considered to be the most significant one. As a result of this incident, reactor operation at full power remained suspended for about 4 years. However, the reactor operation was continued during this period at a power level of 250 kW to cater the needs of various R&D groups, which required lower neutron flux for their experiments. This was made possible by establishing a temporary by pass connection across the decay tank using local technology. The reactor was made operational again at full power after successful replacement of the damaged decay tank in August 2001. At present the reactor is operated 5 days a week at a full power level of 3 MW for production of 1-131 and R&D purposes.Up to December 2005 total burn-up of the core stands at about 358 Megawatt Days (MWDs). BAEC has planned to increase the production of 131I and as such, the core burn-up is expected to be increased very significantly in the years to come. There is a declaration from the US DOE that all US origin research reactor spent fuel generated within 2006 will be taken away to the USA at their own cost within 2009. But the fuel burn up of the BAEC research reactor is about 6%. So the reactor can operate for about 10-20 years more. An initial decommissioning plan for the BAEC TRIGA reactor and relevant facilities should be established as early as possible as recommended in the IAEA Safety Standards Series No.WS-G-2.1 (Decommissioning of Nuclear Power Plants and Research Reactors - Safety Standards Series No.WS-G-2.1, IAEA, Vienna, 1999).During the design and construction phases of the BAEC TRF, aspects to facilitate the decommissioning process and reduce occupational exposures such as selection of material to reduce activation products, use of modular form of items for easy dismantling, designing to avoid contamination or to allow easy decontamination were considered. To reduce contamination and to allow easy decontamination, the floors of the reactor top areas were coated by plastic paint. The primary pumps and demineralization system pump were selected such that all their parts that come in contact with primary coolant were made of high quality stainless steel (ss type 304 and 316). The reactor facility is not susceptible to produce liquid waste in bulk quantity. However, any liquid waste produced in the facility will be processed and, if required, stored in the Central Waste Radioactive Waste Processing and Storage Facility (CWPSF) constructed at the AERE campus and located very close to the reactor facility. CWPSF has been constructed under the project "Establishment of Central Radioactive Waste Processing and Storage Facility" and it is financed by the Government of Bangladesh.During the operational phase of the reactor facility, certain measures are taken into consideration so as to facilitate decommissioning and reduce resource requirements and radiological hazards associated with decommissioning. The measures taken include;the operating history of the facility, including changes of the core components;radiological surveys (radiation and contamination level);modifications to the facility;operation and maintenance records of systems/equipment and design and location of experimental deices used during the operational lifetime of the facility. The paper summarizes the decommissioning plan of the TRIGA Mark-II research reactor of Bangladesh.
机译:孟加拉国原子能委员会(BAEC)的3兆瓦TRIGA Mark-II研究反应堆自1986年9月14日以来一直在运行。该反应堆用于放射性同位素生产(131I,99mTc,46Sc),各种研发活动和人力培训。自调试以来,该反应堆已成功运行,除少数可报告的事件外。其中,1997年的衰减罐泄漏事件被认为是最重要的事件。由于这一事件,反应堆在全功率下的运行暂停了大约4年。但是,在此期间,反应堆以250 kW的功率水平继续运行,以满足各种研发小组的需求,这需要较低的中子通量来进行实验。这是通过使用本地技术跨衰减罐建立临时旁路连接来实现的。在2001年8月成功更换损坏的衰减罐之后,该反应堆又重新投入了全功率运行。目前,该反应堆每周工作5天,以3兆瓦的全功率运行,用于1-131的生产和研发用途。 截至2005年12月,铁心的总燃耗约为358兆瓦日(MWD)。 BAEC已计划增加131I的产量,因此,预计核心燃耗在未来几年将大大增加。美国能源部声明,2006年内所有美国原产研究堆的乏燃料将在2009年以自有成本带到美国。但是,BAEC研究堆的燃料消耗量约为6%。因此该反应堆可以再运行约10-20年。应按照国际原子能机构《安全标准丛书》第WS-G-2.1号(《核电厂和研究堆的退役-安全标准丛书》第WS)条的建议尽早制定BAEC TRIGA反应堆和相关设施的初步退役计划。 -G-2.1,国际原子能机构,维也纳,1999年。 在BAEC TRF的设计和建造阶段中,要进行退役过程并减少职业暴露的方面,例如选择材料以减少活化产品,使用模块化形式的物品以方便拆卸,设计时应避免污染或易于除污。被认为是。为了减少污染并易于除污,在反应器顶部区域的地板上涂了塑料涂料。选择主泵和脱盐系统泵,使得它们与主冷却剂接触的所有部件均由优质不锈钢(ss型304和316)制成。反应器设施不易产生大量废液。但是,设施中产生的所有液体废物都将进行处理,并在需要时将其存储在AERE校园内建造的,非常靠近反应堆设施的中央废物放射性废物处理和储存设施(CWPSF)中。 CWPSF是在“建立中央放射性废物处理和储存设施”项目下建造的,由孟加拉国政府资助。 在反应堆设施的运行阶段,考虑了某些措施,以促进退役并减少资源需求和与退役有关的放射危害。所采取的措施包括;设施的运行历史,包括核心组件的变更;放射学调查(辐射和污染水平);设施的修改;系统/设备的运行和维护记录以及在此期间使用的实验装置的设计和位置设施的使用寿命。本文总结了孟加拉国TRIGA Mark-II研究堆的退役计划。

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