2025
Comprehensive validation of fluorine cross-sections
CZAKOJ, Tomas; Michal KOSTAL; Evzen LOSA; Vojtech RYPAR; Evzen NOVAK et al.Základní údaje
Originální název
Comprehensive validation of fluorine cross-sections
Autoři
CZAKOJ, Tomas; Michal KOSTAL; Evzen LOSA; Vojtech RYPAR; Evzen NOVAK; Martin SCHULC; Bohumil JANSKY; Jiri REJCHRT; Tomas PELTAN; Adam GRES a Zdeněk MATĚJ ORCID
Vydání
ANNALS OF NUCLEAR ENERGY, OXFORD, PERGAMON-ELSEVIER SCIENCE LTD, 2025, 0306-4549
Další údaje
Jazyk
angličtina
Typ výsledku
Článek v odborném periodiku
Obor
10300 1.3 Physical sciences
Stát vydavatele
Velká Británie a Severní Irsko
Utajení
není předmětem státního či obchodního tajemství
Odkazy
Impakt faktor
Impact factor: 2.300 v roce 2024
Označené pro přenos do RIV
Ano
Kód RIV
RIV/00216224:14330/25:00143693
Organizační jednotka
Fakulta informatiky
UT WoS
EID Scopus
Klíčová slova anglicky
Neutron leakage flux; Neutron transport; Fluorine cross-section; 252Cf(s.f) neutron source; Scintillation spectrometer; Hydrogen proportional detector
Změněno: 2. 4. 2026 16:12, RNDr. Pavel Šmerk, Ph.D.
Anotace
V originále
The study utilized a PTFE block with a 252Cf neutron source to measure neutron leakage flux and reaction rate distribution. Hydrogen proportional detectors and stilbene scintillators were employed for spectrum measurement. The experimental setup included various activation foils to measure reaction rates, providing a detailed analysis of neutron interactions with fluorine. The results highlighted discrepancies between measured and calculated neutron spectra, emphasizing the need for continuous refinement of nuclear data libraries. The study compared several libraries, including ENDF/BVIII.0, JEFF-3.3, JENDL-5, and the INDEN fluorine evaluation. It was found that all libraries underpredict measured spectrum in lower energies. Namely below 1.9 MeV in the INDEN fluorine evaluation, below 4.8 MeV in JEFF-3.3 and ENDF/B-VIII.0. JENDL-5 is out of one sigma uncertainty for almost the whole tested energy range. Reaction rate measurements further validated the cross-sections, revealing significant discrepancies in the JENDL-5 library in lower energies. The findings underscore the importance of accurate cross-sections for reliable neutron transport simulations. The study advocates for the adoption of updated cross-sections in nuclear data libraries to enhance simulation accuracy.