Validation of graphite cross section in various integral experiments

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000128" target="_blank" >RIV/26722445:_____/19:N0000128 - isvavai.cz</a>

Result on the web

<a href="https://www.jstage.jst.go.jp/article/jsmeicone/2019.27/0/2019.27_2083/_article" target="_blank" >https://www.jstage.jst.go.jp/article/jsmeicone/2019.27/0/2019.27_2083/_article</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1299/jsmeicone.2019.27.2083" target="_blank" >10.1299/jsmeicone.2019.27.2083</a>

Result language

angličtina

Original language name

Validation of graphite cross section in various integral experiments

Original language description

This paper is focused on validation of graphite cross section. Graphite is an important material for a wide range of reactors such as HTR, RBMK or VHTR and MSR reactors belonging to the generation IV, which are now under development. However, there are still uncertainties in its cross sections. For purposes of mentioned validation, the set of measurements in the LR-0 core with graphite insertion and with graphite cube with external neutron source in its center was carried out. Other types of cores with larger graphite sensitivity are under investigation The cross-section validation by integral experiments is convenient option, because the physical quantities in integral experiments can usually be measured much more accurately than differential nuclear data. And this is also reason why the integral data are widely used for tuning of evaluated cross sections. Data obtained from measurement of neutron leakage spectrum with 252Cf in graphite cube center can be proposed for such kind of adjustments. The results in the LR-0 case are in satisfactory agreement with the calculations performed in MCNP6.1. In the case of leakage spectrum measurement from cube with side of d=30 cm some discrepancies occur. This might imply on incorrect angular treatment in graphite. Such disagreement does not have effect to critical calculations, but might play role in dosimetric calculations in graphite based reactors.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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OECD FORD branch

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

Project

Result was created during the realization of more than one project. More information in the Projects tab.

Continuities

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

Publication year

2019

Confidentiality

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

Article name in the collection

The 27th International Conference on Nuclear Engineering (ICONE27)

ISBN

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ISSN

2424-2934

e-ISSN

2424-2934

Number of pages

7

Pages from-to

1-7

Publisher name

JSME

Place of publication

Japan

Event location

Tsukuba, Ibaraki, Japan

Event date

May 19, 2019

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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