Measurement of Na-23(n,2n) cross section in well-defined reactor spectra

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000010" target="_blank" >RIV/26722445:_____/16:N0000010 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.apradiso.2016.02.003" target="_blank" >http://dx.doi.org/10.1016/j.apradiso.2016.02.003</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.apradiso.2016.02.003" target="_blank" >10.1016/j.apradiso.2016.02.003</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Measurement of Na-23(n,2n) cross section in well-defined reactor spectra

Popis výsledku v původním jazyce

The present paper aims to compare the calculated and experimental reaction rates of Na-23(n,2n)Na-22 in a well-defined reactor spectra of a special core assembled in the LR-0 reactor. The experimentally determined reaction rate, derived using gamma spectroscopy of irradiated NaF sample, is used for average cross section determination. The resulting value averaged in spectra is 0.91 +/- 0.02 mu b. This cross-section is important as it is included in International Reactor Dosimetry and Fusion File and is also relevant to the correct estimation of long-term activity of Na coolant in Sodium Fast Reactors. The calculations were performed with the MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Generally the best CAE agreement, within 2%, was found using the ROSFOND-2010 data set, whereas the worst, as high as 40%, was found using the ENDF/B-VII.0.

Název v anglickém jazyce

Measurement of Na-23(n,2n) cross section in well-defined reactor spectra

Popis výsledku anglicky

The present paper aims to compare the calculated and experimental reaction rates of Na-23(n,2n)Na-22 in a well-defined reactor spectra of a special core assembled in the LR-0 reactor. The experimentally determined reaction rate, derived using gamma spectroscopy of irradiated NaF sample, is used for average cross section determination. The resulting value averaged in spectra is 0.91 +/- 0.02 mu b. This cross-section is important as it is included in International Reactor Dosimetry and Fusion File and is also relevant to the correct estimation of long-term activity of Na coolant in Sodium Fast Reactors. The calculations were performed with the MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Generally the best CAE agreement, within 2%, was found using the ROSFOND-2010 data set, whereas the worst, as high as 40%, was found using the ENDF/B-VII.0.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JF - Jaderná energetika

OECD FORD obor

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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

2016

Kód důvěrnosti údajů

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

Název periodika

Applied Radiation and Isotopes

ISSN

0969-8043

e-ISSN

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Svazek periodika

11

Číslo periodika v rámci svazku

May

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

7

Strana od-do

1-7

Kód UT WoS článku

000374605100001

EID výsledku v databázi Scopus

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