Szczegóły publikacji
Opis bibliograficzny
Underestimation of nuclear fuel burnup – theory, demonstration and solution in numerical models / Paweł GAJDA, Grzegorz KĘPISTY, Michał ORLIŃSKI // E3S Web of Conferences [Dokument elektroniczny]. — Czasopismo elektroniczne ; ISSN 2267-1242. — 2016 — vol. 10 art. no. 00022, s. 1–4. — Wymagania systemowe: Adobe Reader. — Tryb dostępu: https://goo.gl/cMWQn8 [2016-11-07]. — Bibliogr. s. 4, Abstr. — Publikacja dostępna online od: 2016-10-17. — SEED 2016 : 1st international conference on the Sustainable Energy and Environment Development : [Kraków, Poland, May 17th–19th, 2016]
Autorzy (3)
Dane bibliometryczne
| ID BaDAP | 101810 |
|---|---|
| Data dodania do BaDAP | 2016-12-16 |
| DOI | 10.1051/e3sconf/20161000022 |
| Rok publikacji | 2016 |
| Typ publikacji | referat w czasopiśmie |
| Otwarty dostęp |  |
| Creative Commons | |
| Czasopismo/seria | E3S Web of Conferences |
Abstract
Monte Carlo methodology provides reference statistical solution of neutron transport criticality problems of nuclear systems. Estimated reaction rates can be applied as an input to Bateman equations that govern isotopic evolution of reactor materials. Because statistical solution of Boltzmann equation is computationally expensive, it is in practice applied to time steps of limited length. In this paper we show that simple staircase step model leads to underprediction of numerical fuel burnup (Fissions per Initial Metal Atom – FIMA). Theoretical considerations indicates that this error is inversely proportional to the length of the time step and origins from the variation of heating per source neutron. The bias can be diminished by application of predictor-corrector step model. A set of burnup simulations with various step length and coupling schemes has been performed. SERPENT code version 1.17 has been applied to the model of a typical fuel assembly from Pressurized Water Reactor. In reference case FIMA reaches 6.24% that is equivalent to about 60 GWD/tHM of industrial burnup. The discrepancies up to 1% have been observed depending on time step model and theoretical predictions are consistent with numerical results. Conclusions presented in this paper are important for research and development concerning nuclear fuel cycle also in the context of Gen4 systems.
