Abstract
The Subcritical Assembly for Molybdenum-99 Production (SAMOP) system by using low enriched uranyl nitrate solution as reactor fuel is being developed and designed in the Centre for Accelerator Science & Technology, Yogyakarta. The source term analysis of the SAMOP experimental facility is done in conjunction with the radiation shielding design. The method used is by using MCNPX software for fuel burn-up calculations. The burnup calculation is done both in the reactor operation without 99Mo extraction and with 100% 99Mo extraction per batch (6 day + 1 day reactor off) along 1 month operation (5 batch). The calculation was done for two conditions i.e. without and with 99Mo extraction. The calculation result shows that the radioactivity inside the SAMOP reactor core reach 523 Ci for the condition without 99Mo extraction. The effective dose at a distance of 50 cm from the outer surface of the SAMOP reactor coolant tank is 1600 mSv/h. When the SAMOP reactor is operated then followed by 99Mo extraction, the overall radioactivity of the reactor core is slightly lower than the above value. The calculation results also shows that the highest dose from volatile nuclide is caused by 132Te isotope i.e. 92.12 mSv/h.
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