Measurement of Different Neutron Induced Reactions in 252Cf Spontaneous Fission Neutron Spectrum

Kód výsledku v IS VaVaI

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Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Measurement of Different Neutron Induced Reactions in 252Cf Spontaneous Fission Neutron Spectrum

Popis výsledku v původním jazyce

This paper presents the compilation of works performed on the spectrum averaged cross section measurements using the 252Cf spontaneous neutron fission for selected threshold reactions. The irradiated samples were of different sizes, small-volume and large volume samples. Large volume samples were homogenized and strewed into the Marinelli beaker. Small volumes were placed directly on the top surface of the high purity germanium detector. The spectrum averaged cross sections were derived from experimentally determined reaction rates using net peak areas obtained from a semiconductor gamma spectroscopy. Experimental reaction rates were compared with calculations carried out in MCNP6 transport code using IRDFF-v1.05 nuclear data library. Spectral averaged cross sections were also compared with the IRDFF-v1.05 library based on previously measured data by Mannhart where applicable. There is a noticeable disagreement in IRDFF-1.05 library only for 54Fe(n,p)54Mn, 55Mn(n,2n)54Mn and 54Fe(n,α) 51Cr reactions. The presented experimental data can be used to cross section validation. Some of the derived spectral averaged cross sections were integrated into the EXFOR database.

Název v anglickém jazyce

Measurement of Different Neutron Induced Reactions in 252Cf Spontaneous Fission Neutron Spectrum

Popis výsledku anglicky

This paper presents the compilation of works performed on the spectrum averaged cross section measurements using the 252Cf spontaneous neutron fission for selected threshold reactions. The irradiated samples were of different sizes, small-volume and large volume samples. Large volume samples were homogenized and strewed into the Marinelli beaker. Small volumes were placed directly on the top surface of the high purity germanium detector. The spectrum averaged cross sections were derived from experimentally determined reaction rates using net peak areas obtained from a semiconductor gamma spectroscopy. Experimental reaction rates were compared with calculations carried out in MCNP6 transport code using IRDFF-v1.05 nuclear data library. Spectral averaged cross sections were also compared with the IRDFF-v1.05 library based on previously measured data by Mannhart where applicable. There is a noticeable disagreement in IRDFF-1.05 library only for 54Fe(n,p)54Mn, 55Mn(n,2n)54Mn and 54Fe(n,α) 51Cr reactions. The presented experimental data can be used to cross section validation. Some of the derived spectral averaged cross sections were integrated into the EXFOR database.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2018

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Advanced Technologies for Gen. IV Reactors - October 18th 2018

ISBN

978-80-270-5393-3

ISSN

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e-ISSN

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Počet stran výsledku

5

Strana od-do

39-43

Název nakladatele

Centrum výzkumu Řež, s.r.o.

Místo vydání

Řež

Místo konání akce

Řež

Datum konání akce

18. 10. 2018

Typ akce podle státní příslušnosti

EUR - Evropská akce

Kód UT WoS článku

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