2025
Aluminium fast neutron leakage spectrum validation
SCHULC, Martin; Tomas CZAKOJ; Evzen NOVAK; Alena KRECHLEROVA; Adam GRES et al.Základní údaje
Originální název
Aluminium fast neutron leakage spectrum validation
Autoři
SCHULC, Martin; Tomas CZAKOJ; Evzen NOVAK; Alena KRECHLEROVA; Adam GRES; Jan SIMON; Bohumil JANSKY; Jiri REJCHRT; Zdeněk MATĚJ ORCID a Michal KOSTAL
Vydání
RADIATION PHYSICS AND CHEMISTRY, OXFORD, PERGAMON-ELSEVIER SCIENCE LTD, 2025, 0969-806X
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: 3.300 v roce 2024
Označené pro přenos do RIV
Ano
Kód RIV
RIV/00216224:14330/25:00143694
Organizační jednotka
Fakulta informatiky
UT WoS
EID Scopus
Klíčová slova anglicky
Neutron leakage spectrum; Cf-252; Al cross section; Validation; Activation foils
Změněno: 2. 4. 2026 16:12, RNDr. Pavel Šmerk, Ph.D.
Anotace
V originále
Aluminium is a crucial material in the nuclear industry, valued for its reliability over long periods of irradiation. The manuscript focuses on validating aluminium neutron transport libraries. Validation experiments were performed on an aluminium block with a central hole. The block was assembled from smaller aluminium plates. The experiment involved activating samples at different positions and measuring the fast neutron spectrum in the energy range of 0.1 MeV-1.3 MeV by means of a hydrogen-filled proportional detector and in the energy range of 1 MeV-12 MeV using a stilbene scintillation detector. The dosimetric reactions studied for validation included 58Ni(n,p)58Co, 63Cu(n,gamma)64Cu, 181Ta(n,gamma)182Ta, 92Mo(n,p)92mNb, natTi(n,X)46Sc, and natTi(n,X)47Sc. All experimental data were compared with MCNP6.2 simulations using the ENDF/B-VIII.0, JEFF-3.3, and JENDL-5 neutron transport libraries. Activation cross sections were taken from the IRDFF-II library. Regarding activation reactions, the results are in good agreement with simulations, independent on the library. The JEFF-3.3 and ENDF/ B-VIII.0 fast neutron flux calculations are similar. All libraries provided results within two sigma uncertainty, except for JENDL-5 in the energy range of 1.8-3.4 MeV, and ENDF/B-VIII.0 (JEFF-3.3) in the region of 1.06-1.3 MeV.