Počet záznamů: 1
Determination of the Secondary Neutron Flux at the Massive Natural Uranium Spallation Target
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SYSNO ASEP 0506278 Druh ASEP C - Konferenční příspěvek (mezinárodní konf.) Zařazení RIV D - Článek ve sborníku Název Determination of the Secondary Neutron Flux at the Massive Natural Uranium Spallation Target Tvůrce(i) Zeman, M. (CZ)
Adam, Jindřich (UJF-V) RID
Baldin, A. A. (RU)
Furman, W. (RU)
Gustov, S. A. (RU)
Katovsky, K. (CZ)
Khushvaktov, J. (RU)
Mar'in, I. (RU)
Novotný, F. (CZ)
Solnyshkin, A. A. (RU)
Tichý, Pavel (UJF-V) SAI
Tsoupko-Sitnikov, V. M. (RU)
Tyutyunnikov, S. I. (RU)
Vespalec, R. (CZ)
Vrzalová, Jitka (UJF-V) RID, ORCID
Wagner, Vladimír (UJF-V) RID, ORCID, SAI
Závorka, L. (CZ)Celkový počet autorů 17 Zdroj.dok. Physics Procedia, Conference on the Application of Accelerators in Research and Industry (CAARI 2016), 90. - Amsterdam : Elsevier, 2017 - ISSN 1875-3892 Rozsah stran s. 69-78 Poč.str. 10 s. Forma vydání Tištěná - P Akce 24th International Conference on the Application of Accelerators in Research and Industry (CAARI 2016) Datum konání 30.10.2016 - 04.11.2016 Místo konání Los Alamos Země US - Spojené státy americké Typ akce WRD Jazyk dok. eng - angličtina Země vyd. NL - Nizozemsko Klíč. slova ADS ; spallation target ; neutron flux Vědní obor RIV BG - Jaderná, atomová a mol. fyzika, urychlovače Obor OECD Nuclear physics CEP LG14004 GA MŠMT - Ministerstvo školství, mládeže a tělovýchovy Institucionální podpora UJF-V - RVO:61389005 UT WOS 000454340400010 EID SCOPUS 85037700467 DOI 10.1016/j.phpro.2017.09.021 Anotace The flux of secondary neutrons generated in collisions of the 660 MeV proton beam with the massive natural uranium spallation target was investigated using a set of monoisotopic threshold activation detectors. Sandwiches made of thin high-purity Al, Co, Au, and Bi metal foils were installed in different positions across the whole spallation target. The gamma-ray activity of products of (n,xn) and other studied reactions was measured offline with germanium semiconductor detectors. Reaction yields of radionuclides with half-life exceeding 100 min and with effective neutron energy thresholds between 3.6 MeV and 186 MeV provided us with information about the spectrum of spallation neutrons in this energy region and beyond. The experimental neutron flux was determined using the measured reaction yields and cross-sections calculated with the TALYS 1.8 nuclear reaction program and INCL4-ABLA event generator of MCNP6. Neutron spectra in the region of activation sandwiches were also modeled with the radiation transport code MCNPX 2.7. Neutron flux based on excitation functions from TALYS provides a reasonable description of the neutron spectrum inside the spallation target and is in good agreement with Monte-Carlo predictions. The experimental flux that uses INCL4 cross-sections rather underestimates the modeled spectrum in the whole region of interest, but the agreement within few standard deviations was reached as well. The paper summarizes basic principles of the method for determining the spectrum of high-energy neutrons without employing the spectral adjustment routines and points out to the need for model improvements and precise cross-section measurements. Pracoviště Ústav jaderné fyziky Kontakt Markéta Sommerová, sommerova@ujf.cas.cz, Tel.: 266 173 228 Rok sběru 2020
Počet záznamů: 1