{"id":31139,"date":"2026-03-24T08:56:34","date_gmt":"2026-03-24T07:56:34","guid":{"rendered":"https:\/\/www.revistanuclear.es\/?p=31139"},"modified":"2026-03-24T08:58:03","modified_gmt":"2026-03-24T07:58:03","slug":"effect-of-icrp-116-dose-conversion-factors-on-the-doses-due-to-the-isfsis-of-almaraz-cofrentes-and-trillo-npps","status":"publish","type":"post","link":"https:\/\/www.revistanuclear.es\/en\/fuel-cycle\/effect-of-icrp-116-dose-conversion-factors-on-the-doses-due-to-the-isfsis-of-almaraz-cofrentes-and-trillo-npps\/","title":{"rendered":"Effect of ICRP 116 dose conversi\u00f3n factors on the doses due to the ISFSIs of Almaraz, Cofrentes and Trillo NPPs"},"content":{"rendered":"

\"\"<\/span>SEE FULL VERSION<\/span><\/a>
<\/div>D<\/span>uring the period 2015-2021, radiological calculations were performed for the licensing of the Independent Spent Fuel Storage Installations (ISFSIs)<\/strong> currently operating at the Cofrentes NPP (ATI-24), Almaraz NPP (ATI-20), and Trillo NPP. The three ISFSIs use different models of dual purpose (storage and transport) metallic casks<\/strong>: DPT, ENUN 32P, and HI-STAR-150. At the Cofrentes and Almaraz NPPs, the casks are stored on open-air slabs, while at the Trillo NPP they are stored inside a concrete building that provides considerable shielding.<\/span><\/p>\n
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Regulatory update and calculation methodology<\/strong><\/h5>\n<\/div>\n<\/div>\n<\/div>\n<\/div>\n<\/div>\n<\/div>\n<\/section>\n

MAVRIC code<\/strong> (part of Scale package) was used to develop detailed models of the casks, slabs, building, and surrounding areas of each ISFSI. Dose rates were calculated using the fluence to effective dose conversion factors from ICPR publication 74, consistent with the Spanish Regulation on health protection against ionizing radiation of 2001 (Royal Decree 783\/2001)<\/strong> in force at the time the calculations were made. In 2022, a new Spanish Regulation on health protection against risks arising from exposure to ionizing radiation was published (Royal Decree 1029\/2022)<\/strong>, which requires that external exposure calculations follow the methodology set out in ICRP publication 116.<\/strong><\/span><\/p>\n

Comparison between ICRP 74 and ICRP 116 factors<\/strong><\/h5>\n

To determine the effect of the new factors on the radiological calculations of the three aforementioned ISFSIs, the input files of the three ISFSIs<\/strong> were modified to incorporate the conversion factors to effective dose rate from ICRP 116. Dose rates were calculated at different points located outside the ISFSIs<\/strong>, and the results were compared with those obtained in the licensing calculations using the factors from ICRP 74.\u00a0<\/span><\/p>\n

The conversion factors from fluence to effective dose from ICRP 74 and ICRP 116 are very similar for photons of all energies. For neutrons, the ICRP 116 factors are only between 50% and 60% of the ICRP 74<\/strong> values \u200b\u200bfor energies up to 0.05 MeV. For neutrons with energies above 0.05 MeV, the difference between the factors in both publications decreases with increasing energy, and for energies above 0.5 MeV, the factors in both publications are practically the same.<\/span><\/p>\n

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