SCHULC, Martin, Michal KOŠŤÁL, Tomas CZAKOJ, Jan SIMON, Evzen NOVAK a Zdeněk MATĚJ. Comprehensive stainless steel neutron transport libraries validation. ANNALS OF NUCLEAR ENERGY. UNITED STATES: PERGAMON-ELSEVIER SCIENCE LTD, 2022, roč. 179, č. 179, s. 1-7. ISSN 0306-4549. Dostupné z: https://dx.doi.org/10.1016/j.anucene.2022.109433.
Další formáty:   BibTeX LaTeX RIS
Základní údaje
Originální název Comprehensive stainless steel neutron transport libraries validation
Autoři SCHULC, Martin (garant), Michal KOŠŤÁL (203 Česká republika), Tomas CZAKOJ, Jan SIMON, Evzen NOVAK a Zdeněk MATĚJ (203 Česká republika, domácí).
Vydání ANNALS OF NUCLEAR ENERGY, UNITED STATES, PERGAMON-ELSEVIER SCIENCE LTD, 2022, 0306-4549.
Další údaje
Originální jazyk angličtina
Typ výsledku Článek v odborném periodiku
Obor 10304 Nuclear physics
Stát vydavatele Velká Británie a Severní Irsko
Utajení není předmětem státního či obchodního tajemství
WWW URL
Impakt faktor Impact factor: 1.900
Kód RIV RIV/00216224:14330/22:00128562
Organizační jednotka Fakulta informatiky
Doi http://dx.doi.org/10.1016/j.anucene.2022.109433
UT WoS 000860754300006
Klíčová slova anglicky Cf-252; IRDFF-II; Stainless steel; Neutron transport; Leakage neutron spectrum
Změnil Změnil: RNDr. Pavel Šmerk, Ph.D., učo 3880. Změněno: 28. 3. 2023 12:09.
Anotace
Stainless steel is an important material that is relied upon to perform consistently over time in the nuclear industry. The paper focuses on the validation of different stainless steel neutron transport libraries. The validation was performed by means of samples activation in different positions and also the measurement of the fast neutron spectrum in the energy range of 1-12 MeV using a scintillation stilbene detector. Stainless steel was used in the form of a block with a hole for the neutron source. The dosimetric reactions used for validations were Ni-58 (n,p)Co-58, Nb-93(n,2n)Nb-92m, Au-197(n,2n)Au-196, Cu-63(n,g)Cu-64, Au-197(n,g)Au-198, In-115(n,n)In-115m1, In-115(n,g)In-116m1, Mn-55(n,g)Mn-56, and Ta-181(n,g)Ta-182. The experimental data were compared with MCNP6.2 calculations employing ENDF/B-VIII.0, ENDF/B-VII.1, JEFF-3.3, JEFF-3.2, CENDL-3.1, JENDL-5 and INDEN transport libraries. These libraries were used for the simulation of the stainless steel block. The activation foils cross sections were taken from the IRDFF-II library. An intense standard neutron Cf-252(sf) source was placed in the centre of the stainless steel block. INDEN library is the best for the calculation of neutron flux in the range of 1-12 MeV. For the activation detectors placed at the various distances inside the block, the best library depends on the reaction studied.
VytisknoutZobrazeno: 27. 4. 2024 12:22