http://www.colloquiam.com/wd/index.php?action=history&feed=atom&title=Giovacchini_et_al_2021aGiovacchini et al 2021a - Revision history2026-05-15T04:06:51ZRevision history for this page on the wikiMediaWiki 1.27.0-wmf.10http://www.colloquiam.com/wd/index.php?title=Giovacchini_et_al_2021a&diff=226950&oldid=prevScipediacontent: Scipediacontent moved page Draft Content 662251252 to Giovacchini et al 2021a2021-07-12T06:37:31Z<p>Scipediacontent moved page <a href="/public/Draft_Content_662251252" class="mw-redirect" title="Draft Content 662251252">Draft Content 662251252</a> to <a href="/public/Giovacchini_et_al_2021a" title="Giovacchini et al 2021a">Giovacchini et al 2021a</a></p>
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<td colspan='1' style="background-color: white; color:black; text-align: center;">Revision as of 06:37, 12 July 2021</td>
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</td></tr></table>Scipediacontenthttp://www.colloquiam.com/wd/index.php?title=Giovacchini_et_al_2021a&diff=226949&oldid=prevScipediacontent: Created page with "== Abstract == In this work the thermal-hydraulics and neutronics behavior of a Lead Fast Reactor (LFR) core is investigated evaluating the power generation distribution taki..."2021-07-12T06:37:29Z<p>Created page with "== Abstract == In this work the thermal-hydraulics and neutronics behavior of a Lead Fast Reactor (LFR) core is investigated evaluating the power generation distribution taki..."</p>
<p><b>New page</b></p><div>== Abstract ==<br />
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In this work the thermal-hydraulics and neutronics behavior of a Lead Fast Reactor (LFR) core is investigated evaluating the power generation distribution taking into account the local temperature field. The temperature field is evaluated using the CFD finite element code FEMuS and exchanged with the multiscale neutron code DONJON-DRAGON, which interpolates the macroscopic cross-sections according to the local temperature field and local lead density distribution. As a result, the neutron flux changes and defines a new power density distribution which is used to update the temperature field into the CFD code. The coupling between neutron and CFD codes is achieved through their inclusion into the numerical platform SALOME. The numerical libraries MED, included into the SALOME platform, are used to exchange data run-time between FEMuS and DONJON.<br />
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== Full document ==<br />
<pdf>Media:Draft_Content_662251252P_IDC13_376.pdf</pdf></div>Scipediacontent