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Obliczenia neutronowe reaktora AP1000

Suchcicki Szymon

Postępy Techniki Jądrowej

2021

z. 4

2--6

W artykule przedstawiono opis obliczeń neutronowych przeprowadzonych w Państwowej Agencji Atomistyki dla reaktora AP1000. Zaprezentowano krótką charakterystykę tego reaktora, opisano zastosowane kody obliczeniowe oraz przedstawiono wyniki obliczeń i ich porównanie z wynikami zawartymi w amerykańskim raporcie „AP1000 Design Control Document”. Przedstawiono również plany dalszego wykorzystania stworzonych modeli obliczeniowych.

The paper presents a description of neutronic calculations for the AP1000 reactor performed at the National Atomic Energy Agency of the Republic of Poland (PAA). A short characteristic of the reactor is presented, applied computer codes are described and results of the calculations and their comparison with results included in the "AP1000 Design Control Document" are presented. Plans for further use of the created computational models are also discussed.

Obliczenia neutronowe z użyciem kodów SCALE i PARCS

Staroń E., Suchcicki S.

Postępy Techniki Jądrowej

2016

z. 3

17--22

W artykule przedstawiono opis wybranych zagadnień związanych z neutroniką, głównie dotyczących stosowanego oprogramowania oraz łączenia obliczeń neutronowych z cieplno-przepływowymi. Przytoczono również fragmenty wymagań dozorowych odnoszących się do zagadnień neutronowych.

Selected issues dealing with neutronics, mainly concerning the software and coupled neutronic and thermal- -hydraulic calculations are described in this paper. Also, elements of regulatory requirements regarding neutronics issues are included.

Production of fission product 99Mo using high-enriched uranium plates in Polish nuclear research reactor MARIA: Technology and neutronic analysis

Jaroszewicz J., Marcinkowska Z., Pytel K.

Nukleonika

2014

Vol. 59, No. 2

43--52

The main objective of 235U irradiation is to obtain the 99mTc isotope, which is widely used in the domain of medical diagnostics. The decisive factor determining its availability, despite its short lifetime, is a reaction of radioactive decay of 99Mo into 99mTc. One of the possible sources of molybdenum can be achieved in course of the 235U fission reaction. The paper presents activities and the calculation results obtained upon the feasibility study on irradiation of 235U targets for production of 99Mo in the MARIA research reactor. Neutronic calculations and analyses were performed to estimate the fission products activity for uranium plates irradiated in the reactor. Results of dummy targets irradiation as well as irradiation uranium plates have been presented. The new technology obtaining 99Mo is based on irradiation of high-enriched uranium plates in standard reactor fuel channel and calculation of the current fission power generation. Measurements of temperatures and the coolant flow in the molybdenum installation carried out in reactor SAREMA system give online information about the current fission power generated in uranium targets. The corrective factors were taken into account as the heat generation from gamma radiation from neighbouring fuel elements as well as heat exchange between channels and the reactor pool. The factors were determined by calibration measurements conducted with aluminium mock-up of uranium plates. Calculations of fuel channel by means of REBUS code with fine mesh structure and libraries calculated by means of WIMS-ANL code were performed.