TAILIEUCHUNG - Nuclear data uncertainty analysis for the Po-210 production in MYRRHA

MYRRHA is a multi-purpose research reactor able to operate in sub-critical and critical modes and currently in the design phase at SCK•CEN. The choice of LBE was driven by its chemical stability, low melting temperature, high boiling point, low chemical reactivity with water and air and a good neutronic performance. | Nuclear data uncertainty analysis for the Po-210 production in MYRRHA EPJ Nuclear Sci. Technol. 4 48 2018 Nuclear Sciences L. Fiorito et al. published by EDP Sciences 2018 amp Technologies https epjn 2018044 Available online at https REGULAR ARTICLE Nuclear data uncertainty analysis for the Po-210 production in MYRRHA Luca Fiorito1 Alexey Stankovskiy2 Augusto Hernandez-Solis2 Gert Van den Eynde2 and Gasper Zerovnik3 1 Nuclear Energy Agency Data Bank 46 Quai Alphonse le Gallo 92100 Boulogne-Billancourt France 2 SCK CEN Belgian Nuclear Research Center Boeretang 200 2400 Mol Belgium 3 European Commission Joint Research Centre Retieseweg 111 2440 Geel Belgium Received 7 December 2017 Received in final form 7 February 2018 Accepted 8 June 2018 Abstract. MYRRHA is a multi-purpose research reactor able to operate in sub-critical and critical modes and currently in the design phase at SCK CEN. The choice of LBE was driven by its chemical stability low melting temperature high boiling point low chemical reactivity with water and air and a good neutronic performance. As a drawback the neutron capture in 209Bi results in the production of 210Po a highly radiotoxic alpha emitter with relatively short half-life 138 days . The 210Po production represents a major safety concern that has to be addressed for the reactor licensing. In this work we used the ALEPH-2 burnup code to accurately calculate the 210 Po production in a MYRRHA operating cycle. The impact of using different nuclear data libraries was evaluated and the reliability of the results was determined by quantifying the uncertainty of the 210Po concentration. The uncertainty quantification was carried out sampling the currently available nuclear data covariance matrices with the SANDY code. Also estimates of the sensitivity profiles were obtained with a linear regression approach. The activation yield of the 209Bi neutron capture reaction was assessed as the largest nuclear data source of .

• Năng lượng
• Multi purpose research reactor
• Sub critical and critical modes
• Choice of LBE
• Low melting temperature
• Po 210 production
• Dispersed U3Si2 Al
• Open tank in pool
• Equilibrium core
• Shutdown margin
• MW multipurpose research reactor
• Nuclear science and technology
• The journal of Nuclear science and technology
• Full core conversion
• Multipurpose research reactor