Measurement of selected differential cross sections in 235U spectrum

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000014" target="_blank" >RIV/26722445:_____/19:N0000014 - isvavai.cz</a>

Výsledek na webu

<a href="https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/5/3/030906/725875/Measurement-of-Selected-Differential-Cross?redirectedFrom=fulltext" target="_blank" >https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/5/3/030906/725875/Measurement-of-Selected-Differential-Cross?redirectedFrom=fulltext</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1115/1.4042850" target="_blank" >10.1115/1.4042850</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Measurement of selected differential cross sections in 235U spectrum

Popis výsledku v původním jazyce

This paper describes the measurement of Mn-55(n,2n) and I-127(n,2n) reaction rates in a well-defined reactor field in a special core of LR-0 reactor. The reaction rates were derived using gamma-spectrometry by measuring gamma activities of irradiated MnO2 and NaI samples at a high purity germanium (HPGe) detector. The spectral average cross section (SACS) in U-235 prompt fission neutron spectrum (PFNS) was experimentally determined to be 0.2393 +/- 0.015 x 10(-3) b for Mn-55 and 1.2087 +/- 0.052 x 10(-3) b for I-127. These obtained results were compared with calculations by MCNP6 code using ENDF/B VII.1, ENDF/B VII, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010, CENDL-3.1, and IRDFF nuclear data libraries. In a case of Mn-55, a good agreement with ENDF/B VII.1, JEFF 3.1, JENDL 3.3, JENDL 4, ROSFOND, and CENDL 3.1 nuclear data libraries was found, where C/E-1 is 0.1%, while IRDFF underestimated by about 15.8%. In the case of I-127, more significant discrepancies were found, where JENDL 3.3 and JENDL 4 overestimate the result by about 31.3%.

Název v anglickém jazyce

Measurement of selected differential cross sections in 235U spectrum

Popis výsledku anglicky

This paper describes the measurement of Mn-55(n,2n) and I-127(n,2n) reaction rates in a well-defined reactor field in a special core of LR-0 reactor. The reaction rates were derived using gamma-spectrometry by measuring gamma activities of irradiated MnO2 and NaI samples at a high purity germanium (HPGe) detector. The spectral average cross section (SACS) in U-235 prompt fission neutron spectrum (PFNS) was experimentally determined to be 0.2393 +/- 0.015 x 10(-3) b for Mn-55 and 1.2087 +/- 0.052 x 10(-3) b for I-127. These obtained results were compared with calculations by MCNP6 code using ENDF/B VII.1, ENDF/B VII, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010, CENDL-3.1, and IRDFF nuclear data libraries. In a case of Mn-55, a good agreement with ENDF/B VII.1, JEFF 3.1, JENDL 3.3, JENDL 4, ROSFOND, and CENDL 3.1 nuclear data libraries was found, where C/E-1 is 0.1%, while IRDFF underestimated by about 15.8%. In the case of I-127, more significant discrepancies were found, where JENDL 3.3 and JENDL 4 overestimate the result by about 31.3%.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

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

2019

Kód důvěrnosti údajů

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

Název periodika

Journal of Nuclear Engineering and Radiation Science

ISSN

2332-8983

e-ISSN

2332-8975

Svazek periodika

5

Číslo periodika v rámci svazku

3

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

8

Strana od-do

1-8

Kód UT WoS článku

000470245100007

EID výsledku v databázi Scopus

2-s2.0-85070831802