Naslov
Comparison Between ORIGEN2.2 and ORIGEN-S Calculated Source Term

Autori
Grgić, Davor ; Ječmenica, Radomir ; Vlahović, Štefica ; Šadek, Siniša ; Bašić, Ivica

Vrsta, podvrsta i kategorija rada
Sažeci sa skupova, sažetak, znanstveni

Izvornik
Book of Abstracts of the 27th International Conference Nuclear Energy for New Europe NENE2018 / - , 2018, 66-66

Skup
27th International Conference Nuclear Energy for New Europe NENE2018

Mjesto i datum
Portorož, Slovenija, 10.09.2018. - 13.09.2018

Vrsta sudjelovanja
Poster

Vrsta recenzije
Međunarodna recenzija

Ključne riječi
PWR fuel, decay heat, activity, source term, dry storage

Sažetak
The prediction of the nuclear fuel inventory is important in all phases of nuclear fuel stay in reactor, spent fuel pool or dry storage. Typically, decay heat calculation is needed to ensure heat removal, the knowledge of activity is important to model transport of radioactive material in case of any accident leading to cladding damage, and prediction of neutron and gamma source is needed for shielding calculation. Most widely used code able to calculate change in nuclear fuel isotopic content is ORIGEN. Its old version, ORIGEN2.2, is simple to use executable with rather small set of libraries produced for different reactor types and with simple input able to simulate any kind of fuel depletion and decay. New version is ORIGEN-S and it is distributed as part of SCALE package. It has many detailed libraries generated for specific reactor types and it is together with its auxiliary modules (ARP, OPUS, ORIGAMI) accessible through SCALE driver sequence. It uses advanced, object oriented input scheme rather different from old one. It is possible to prepare customized neutron cross sections libraries using t-depl TRITON based sequence. The use of new code can be complicated and code ORIGAMI is developed for computing assembly isotopics based on ORIGEN-S calculation. Still, the usage of new code version is more complicated than old one and it is more difficult to include it in user developed application. We wanted to see what is difference in obtained results, in terms of isotopic inventory, decay heat, activity and neutron and gamma source, when old and new versions are used according to their respective recommended procedures. Both codes were applied to NPP Krsko spent fuel and focus was limited to the calculation needed in the case of dry spent fuel storage. Krsko specific 16x16 arplib libraries were generated for ORIGEN-S and generic PWRUE library was used for ORIGEN2.2. The real fuel assemblies having different enrichment, acquired burnup and cooling times were analyzed. The obtained differences in terms of decay heat and activity were within 10%, with new version being more conservative for high burnup and less conservative for low burnup fuel. The information available for neutron and gamma sources are not completely the same in both code versions, but where the values are available in the same format the differences are within 15%. Based on performed calculations and obtained results we can say that we will continue to use both versions, old code version where fast scoping calculation of large number of assemblies is needed and new one if we need more accuracy or in case of neutron and gamma source preparation for Monte Carlo codes.

Izvorni jezik
Engleski

POVEZANOST RADA