Lithuanian Journal of Physics article / Lietuvos fizikos žurnalo straipsnis

GENERATION OF RBMK-1500 SPENT NUCLEAR FUEL ONE-GROUP CROSS-SECTION LIBRARIES AND THEIR EVALUATION AGAINST EXPERIMENTAL DATA
Vytenis Barkauskas, Rita Plukienė, Artūras Plukis, and Vidmantas Remeikis
Institute of Physics, Center for Physical Sciences and Technology, Savanorių 231, LT-02300 Vilnius, Lithuania
E-mail: office@ftmc.lt; vytenis.barkauskas@ftmc.lt

Received 1 July 2016; revised 13 October 2016; accepted 21 December 2016

Depletion of RBMK-1500 spent nuclear fuel (SNF) with and without an erbium burnable absorber was modelled, and one-group burn-up dependent cross-section libraries for Origen-ARP were created. Depletion calculations for the generation of cross-section libraries were performed using the SCALE 6.1 code package with the TRITON control module, which employs the NEWT deterministic 2D transport code with the 238-group energy library based on the ENDF-B VII library and the ORIGEN-S nuclide composition calculation code. Concentrations of the most important actinides for criticality safety were calculated using the created libraries and were compared with the available experimental data and the newest modelling results. Available experimental data of fission products (Nd and Cs isotopes) were also compared to the modelling results. Composition differences were evaluated for several fuel enrichments and water densities. The comparison shows an acceptable agreement between the values obtained using new one-group cross-section libraries and experimental data except for ²³⁸Pu and ²⁴¹Am, as well as the causes of discrepancy are discussed. It has been found that the enrichment and presence of the burnable absorber play an important role in the SNF composition. At the highest evaluated burn-up (29 GWd/tU) isotopic composition differences between 2% enrichment fuel and 2.8% burn-up for actinides important to burn-up credit (BUC) applications varied from 11 to 52%.

Keywords: RBMK-1500 reactor, spent nuclear fuel, actinides, SCALE 6.1 modelling, one-group cross-sections
PACS: 28.41.Ak, 28.41.Kw, 28.50.Hw

RBMK-1500 PANAUDOTO BRANDUOLINIO KURO SKERSPJŪVIŲ BIBLIOTEKŲ SUDARYMAS IR JŲ ĮVERTINIMAS ATSIŽVELGIANT Į EKSPERIMENTINIUS DUOMENIS

Vytenis Barkauskas, Rita Plukienė, Artūras Plukis, Vidmantas Remeikis
Fizinių ir technologijos mokslų centro Fizikos institutas, Vilnius, Lietuva

Skaitmeniškai modeliuotas RBMK-1500 reaktoriaus skirtingai įsodrinto kuro nuklidinės sudėties kitimas reaktoriuje. Modeliuojant sudarytos vienos energijos grupės skerspjūvių bibliotekos, skirtos Origen-ARP programai. Nuklidinės sudėties kitimo skaičiavimai atlikti naudojantis SCALE 6.1 programų paketo TRITON moduliu, kuriame neutronų pernašos lygtis sprendžiama su NEWT deterministinio skaičiavimo programa. Skaičiavimams naudota 238 energijos grupių nuklidų skerspjūvių biblioteka ENDF-B VII. Apšvitinto branduolinio kuro nuklidinė sudėtis įvertinta su ORIGEN-S programa. Naudojantis sudarytomis vienos grupės bibliotekomis buvo įvertintos kritiškumo saugai svarbiausių aktinoidų koncentracijos ir jos palygintos su prieinamais eksperimentiniais duomenimis bei kitų mokslininkų skaičiavimų rezultatais. Su eksperimentiniais duomenimis taip pat palygintos ir dalijimosi produktų (Cs ir Nd izotopų) koncentracijos. Nustatyti sudėties skirtumai esant skirtingam branduolinio kuro įsodrinimui ir šilumnešio (vandens) tankiui eksploatavimo metu. Palyginimas rodo patenkinamą nuklidų koncentracijų skaitinio modeliavimo ir eksperimentinių verčių atitikimą, išskyrus ²³⁸Pu ir ²⁴¹Am nuklidų koncentracijas. Darbe aptartos šių neatitikimų priežastys. Nustatyta, kad įsodrinimas ir išdegantis sugėriklis turi didelę įtaką panaudoto branduolinio kuro sudėčiai. Esant didžiausiai analizuotai išdegimo vertei (29 GWd/tU) kritiškumo saugai svarbių aktinoidų koncentracijų skirtumai nuo 2 iki 2,8 % įsodrinimo kuro sudarė 11–52 %.

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