izpis_h1_title_alt

Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique
ID Goričanec, Tanja (Avtor), ID Kos, Bor (Avtor), ID Ambrožič, Klemen (Avtor), ID Trkov, Andrej (Avtor), ID Snoj, Luka (Avtor), ID Kromar, Marjan (Avtor)

.pdfPDF - Predstavitvena datoteka, prenos (63,84 MB)
MD5: 6FB304952EAF2AEA18957CCB76134FCA
URLURL - Izvorni URL, za dostop obiščite https://www.frontiersin.org/articles/10.3389/fenrg.2023.1137867/full Povezava se odpre v novem oknu

Izvleček
In a typical pressurized water reactor, neutron detectors located outside the reactor core monitor reactor power. In addition, they are also used to measure the reactivity of the control rods. A novel approach to calculate the ex-core neutron detector response in a typical pressurized water reactor using the Monte Carlo technique is presented. A detailed ex-core model of the Krško nuclear power plant was developed using the Monte Carlo neutron transport code MCNP. Due to the location of the ex-core neutron detectors, the hybrid code ADVANTG is used to generate variance reduction parameters to accelerate the convergence of the results outside the reactor core. To use ADVANTG, the fixed neutron source had to be reconstructed from the criticality core calculation. This paper presents the sensitivity analysis of the response of the ex-core detectors to the neutron data libraries used, the description of the fixed neutron source and the ADVANTG parameters. It was found that a pin-wise description of the neutron source for at least two rows of fuel assemblies at the core periphery is necessary for accurate results. Our results show the importance of a correct description of the prompt neutron spectra in the high energy region and the impact this has on the response of the ex-core detectors. The method in which the prompt neutron fission spectra for important fission nuclides are weighted by the calculated reaction rates has been shown to be the best approximation, with deviations from the reference calculation within statistical uncertainty. The effect of nuclear data libraries on the response of the ex-core detector was investigated, and the difference between the ENDF/B-VII.0 and the ENDF/B-VIII.0 nuclear data libraries was ∼11%. When the deficient evaluation of the $^{56}$Fe isotope included in the ENDF/B-VIII.0 nuclear data library was replaced by the improved evaluation from the IAEA INDEN project, the differences decreased to ∼3.7%. In addition, neutron flux redistributions due to control rod movement were investigated and flux redistribution factors were updated using Monte Carlo particle transport methods. The reaction rate redistribution factors obtained with methods presented in this paper are within 1% agreement with the currently used factors.

Jezik:Angleški jezik
Ključne besede:MCNP, ADVANTG, pressurized water reactor, Monte Carlo neutron transport, control rod, neutron flux redistribution factor, rod insertion, Krško nuclear power plant
Vrsta gradiva:Članek v reviji
Tipologija:1.01 - Izvirni znanstveni članek
Organizacija:FMF - Fakulteta za matematiko in fiziko
Status publikacije:Objavljeno
Različica publikacije:Objavljena publikacija
Leto izida:2023
Št. strani:20 str.
Številčenje:Vol. 11, art. 1137867
PID:20.500.12556/RUL-155256 Povezava se odpre v novem oknu
UDK:539.1
ISSN pri članku:2296-598X
DOI:10.3389/fenrg.2023.1137867 Povezava se odpre v novem oknu
COBISS.SI-ID:142840067 Povezava se odpre v novem oknu
Datum objave v RUL:22.03.2024
Število ogledov:241
Število prenosov:31
Metapodatki:XML RDF-CHPDL DC-XML DC-RDF
:
Kopiraj citat
Objavi na:Bookmark and Share

Gradivo je del revije

Naslov:Frontiers in energy research
Skrajšan naslov:Front. energy res.
Založnik:Frontiers Media
ISSN:2296-598X
COBISS.SI-ID:27719207 Povezava se odpre v novem oknu

Licence

Licenca:CC BY 4.0, Creative Commons Priznanje avtorstva 4.0 Mednarodna
Povezava:http://creativecommons.org/licenses/by/4.0/deed.sl
Opis:To je standardna licenca Creative Commons, ki daje uporabnikom največ možnosti za nadaljnjo uporabo dela, pri čemer morajo navesti avtorja.

Sekundarni jezik

Jezik:Slovenski jezik
Ključne besede:jedrska fizika, jedrski reaktor

Projekti

Financer:ARRS - Agencija za raziskovalno dejavnost Republike Slovenije
Številka projekta:L2-8163
Naslov:Razvoj metod za izračun nevtronskega polja v zadrževalnem hramu tlačnovodne jedrske elektrarne

Financer:ARRS - Agencija za raziskovalno dejavnost Republike Slovenije
Številka projekta:L2-2612
Naslov:Stabilnost jedrskih reaktorjev pri obratovanju v načinu sledenja bremenu

Financer:ARRS - Agencija za raziskovalno dejavnost Republike Slovenije
Številka projekta:P2-0073
Naslov:Reaktorska fizika

Podobna dela

Podobna dela v RUL:
Podobna dela v drugih slovenskih zbirkah:

Nazaj