J 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

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.