Development in Studsvik’s system for spent fuel analyses
26th Symposium of AER on VVER Reactor Physics and Reactor Safety (2016, Helsinki, Finland)
Intermediate storage of spent fuel decommissioning and radwaste / Spent fuel disposal and actinide transmutation
Abstract
DEVELOPMENT IN STUDSVIK’S SYSTEM FOR SPENT FUEL ANALYSESTeo Simeonov, Charles Wemple Studsvik Scandpower Inc teodosi.simeonov@studsvik.com charles.wemple@studsvik.comABSTRACTThe ongoing development of the system for spent fuel analyses at Studsvik aims to meet and fulfill a broad spectrum of backend reactor analyses, ranging from the very basic – isotopic concentrations, residual heat and activities – to support for cask loading procedures and accident analyses. The success of the SNF code among the utilities, research institutions, and national authorities is due to its best estimate methodology, combined with incomparable user friendliness, elaborate engineering functionality, and the ability to compute the spent fuel characteristics in real time over an entire reactor core and reactor spent fuel pool. Studsvik’s approach to spent nuclear fuel analyses combines isotopic data calculated by the CASMO5 or HELIOS2 lattice transport codes, with core irradiation history data from the 3D reactor simulator, and isotopic decay data. The overview in this paper aims to demonstrate the enhanced applicability of SNF as result of extensions and improvements in the methodologies in all three directions: lattice physics transport calculations, irradiation history, and decay data.KEYWORDS: spent nuclear fuel, decay library, ENDF/B-VII, SNF, CASMO5, HELIOS2 26th Symposium of AER on VVER Reactor Physics and Reactor Safety 59 10 – 14 October 2016, Helsinki, Finland