Measurement of As-75(n,2n) cross section in well-defined spectrum of LR-0 special core

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F17%3AN0000041" target="_blank" >RIV/26722445:_____/17:N0000041 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0306454916309306" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0306454916309306</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2016.10.012" target="_blank" >10.1016/j.anucene.2016.10.012</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Measurement of As-75(n,2n) cross section in well-defined spectrum of LR-0 special core

Popis výsledku v původním jazyce

The article describes measurement of the As-75(n,2n)As-74 reaction rate in a well-defined reactor spectrum of a special core assembled in the LR-0 reactor. It presents a comparison of this value with results of calculations. The reaction rate is derived from activity of As-74 which is determined using gamma spectrometry of an irradiated As2O3 sample. The resulting value averaged in reactor spectrum is 77.0 +/- 3.90 mu b. This cross section is important as it is included as neutron flux monitor in the International Reactor Dosimetry and Fusion File. The calculations were carried out with the MCNP6 code using ENDF/B-VII.0, ENDF/B-VII.1 JEFF-3.1, JEFF-3,2, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. The comparison between calculation and experiment shows very good agreement. The relative difference between calculation and experiment is lower than the related uncertainty in all cases. The discrepancy is even below 1% with ENDF/B-VII.1 and JEFF-3.2.

Název v anglickém jazyce

Measurement of As-75(n,2n) cross section in well-defined spectrum of LR-0 special core

Popis výsledku anglicky

The article describes measurement of the As-75(n,2n)As-74 reaction rate in a well-defined reactor spectrum of a special core assembled in the LR-0 reactor. It presents a comparison of this value with results of calculations. The reaction rate is derived from activity of As-74 which is determined using gamma spectrometry of an irradiated As2O3 sample. The resulting value averaged in reactor spectrum is 77.0 +/- 3.90 mu b. This cross section is important as it is included as neutron flux monitor in the International Reactor Dosimetry and Fusion File. The calculations were carried out with the MCNP6 code using ENDF/B-VII.0, ENDF/B-VII.1 JEFF-3.1, JEFF-3,2, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. The comparison between calculation and experiment shows very good agreement. The relative difference between calculation and experiment is lower than the related uncertainty in all cases. The discrepancy is even below 1% with ENDF/B-VII.1 and JEFF-3.2.

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

2017

Kód důvěrnosti údajů

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

Název periodika

Annals of Nuclear Energy

ISSN

0306-4549

e-ISSN

—

Svazek periodika

100

Číslo periodika v rámci svazku

2

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

8

Strana od-do

42-49

Kód UT WoS článku

000390746700005

EID výsledku v databázi Scopus

2-s2.0-84994735127