Validation of graphite cross section in various integral experiments

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

Validation of graphite cross section in various integral experiments

Popis výsledku v původním jazyce

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. Copyright 2018-2019 by JSME

Název v anglickém jazyce

Validation of graphite cross section in various integral experiments

Popis výsledku anglicky

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. Copyright 2018-2019 by JSME

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

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Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název statě ve sborníku

The Proceedings of the International Conference on Nuclear Engineering (ICONE)

ISBN

978-4-88898-305-1

ISSN

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e-ISSN

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Počet stran výsledku

6

Strana od-do

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Název nakladatele

Japan Society of Mechanical Engineers

Místo vydání

Tokyo

Místo konání akce

Tsukuba

Datum konání akce

19. 5. 2019

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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