J 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

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.