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Feder, Russell E.; Youssef, Mahmoud Z.
Princeton Plasma Physics Lab., Princeton, NJ (United States). Funding organisation: USDOE Office of Science (United States)2009
Princeton Plasma Physics Lab., Princeton, NJ (United States). Funding organisation: USDOE Office of Science (United States)2009
AbstractAbstract
[en] Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support of the integration of diagnostics in to the ITER Upper Port Plugs. Simplified shielding models of the Visible-Infrared diagnostic and of a large aperture diagnostic were incorporated in to the ITER global CAD model. Results for these systems are representative of typical designs with maximum shielding and a small aperture (Vis-IR) and minimal shielding with a large aperture. The neutronics discrete-ordinates code ATTILA(regsign) and SEVERIAN(regsign) (the ATTILA parallel processing version) was used. Material properties and the 500 MW D-T volume source were taken from the ITER 'Brand Model' MCNP benchmark model. A biased quadrature set equivalent to Sn=32 and a scattering degree of Pn=3 were used along with a 46-neutron and 21-gamma FENDL energy subgrouping. Total nuclear heating (neutron plug gamma heating) in the upper port plugs ranged between 380 and 350 kW for the Vis-IR and Large Aperture cases. The Large Aperture model exhibited lower total heating but much higher peak volumetric heating on the upper port plug structure. Personnel dose rates are calculated in a three step process involving a neutron-only transport calculation, the generation of activation volume sources at pre-defined time steps and finally gamma transport analyses are run for selected time steps. ANSI-ANS 6.1.1 1977 Flux-to-Dose conversion factors were used. Dose rates were evaluated for 1 full year of 500 MW DT operation which is comprised of 3000 1800-second pulses. After one year the machine is shut down for maintenance and personnel are permitted to access the diagnostic interspace after 2-weeks if dose rates are below 100 (micro)Sv/hr. Dose rates in the Visible-IR diagnostic model after one day of shutdown were 130 (micro)Sv/hr but fell below the limit to 90 (micro)Sv/hr 2-weeks later. The Large Aperture style shielding model exhibited higher and more persistent dose rates. After 1-day the dose rate was 230 (micro)Sv/hr but was still at 120 (micro)Sv/hr 4-weeks later.
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28 Jan 2009; 8 p; 36. International Conference on Plasma Science (ICOPS); San Diego, CA (United States); 31 May - 5 Jun 2009; 23. Symposium on Fusion Engineering (SOFE); San Diego, CA (United States); 31 May - 5 Jun 2009; ACO2-09CH11466; Also available from OSTI as DE00964190; PURL: https://www.osti.gov/servlets/purl/964190-ynrvLH/; doi 10.2172/953485
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