Wyniki wyszukiwania - BazTech

1

Obliczenia neutronowe reaktora AP1000

Suchcicki Szymon

Postępy Techniki Jądrowej

|

2021

|

z. 4

2--6

PL

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.

EN

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.

2

Analysis of the BEAVRS PWR benchmark using SCALE and PARCS

Darnowski Piotr, Pawluczyk Michał

Nukleonika

|

2019

|

Vol. 64, No. 3

87--96

EN

This paper presents an analysis of the Benchmark for Evaluation And Validation of Reactor Simulations (BEAVRS) performed using SCALE 6.1.2 and PARCS 3.2 computer codes. The benchmark specifi cation contains a detailed design, operational data and measurements for a real 4-loop Westinghouse pressurized water reactor (PWR). The lattice physics simulations were prepared using TRITON depletion sequence and NEWT neutron transport solver (SCALE package). The 238-neutron group library based on evaluated nuclear data fi le – ENDF/B-VII nuclear data libraries was applied. A set of branch and burnup calculations was prepared, and group constants in the form of PMAXS fi les were generated with GenPMAXS. The full-core models were prepared using the PARCS nodal-diffusion core simulator. The PMAXS libraries were used with PARCS to investigate the core operation. The hot zero power measurement data, including control rod worths and critical boron concentrations, were compared using simulations, and satisfactory results were achieved. The fi rst fuel cycle was simulated, and acceptable agreement with boron letdown curve and measurements were obtained. Finally, conclusions and recommendations for future research were presented.

3

Obliczenia neutronowe z użyciem kodów SCALE i PARCS

Staroń E., Suchcicki S.

Postępy Techniki Jądrowej

|

2016

|

z. 3

17--22

PL

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.

EN

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.