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Performance of ENDF/B-VIII.0 library for VVER reactors criticality safety, fuel depletion and reactor dosimetry applications

Identifikátory výsledku

  • Kód výsledku v IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F20%3A43959200" target="_blank" >RIV/49777513:23220/20:43959200 - isvavai.cz</a>

  • Výsledek na webu

    <a href="https://www.sciencedirect.com/science/article/pii/S0306454920304345" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0306454920304345</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.anucene.2020.107736" target="_blank" >10.1016/j.anucene.2020.107736</a>

Alternativní jazyky

  • Jazyk výsledku

    angličtina

  • Název v původním jazyce

    Performance of ENDF/B-VIII.0 library for VVER reactors criticality safety, fuel depletion and reactor dosimetry applications

  • Popis výsledku v původním jazyce

    The latest ENDF/B nuclear data library released in 2018 is the result of a new international approach to develop evaluated nuclear data for general purpose applications. In order to use the latest ENDF/B-VIII.0 nuclear data library in safety analyses, validation calculations for available benchmark experiments and comparison calculations for previous library versions are required. Validation of this new library for three important reactor areas, criticality safety, fuel depletion and reactor dosimetry, was performed with MCNP6, KENO-VI and Serpent 2 codes for VVER application. Criticality safety and fuel depletion results show better agreement with ICSBEP and SFCOMPO benchmark database cases for the ENDF/B-VIII.0 library when compared with previous libraries including ENDF/B-VII.1. On the other hand, using the latest VIII.0 library for VVER reactor dosimetry applications including neutron fluence on reactor pressure vessel and ex-vessel neutron fluence activation monitors is not recommended since the library gives significantly lower neutron fluence and detector activities when comparing to number of alternative nuclear data libraries. Two nuclides that are dominantly responsible for the discrepancies between the latest ENDF/B library and other libraries were identified as O-16 and Fe-56. The conclusions are limited to VVER application where the water gap between the reactor core and the pressure vessel is significantly decreased compared to PWR.

  • Název v anglickém jazyce

    Performance of ENDF/B-VIII.0 library for VVER reactors criticality safety, fuel depletion and reactor dosimetry applications

  • Popis výsledku anglicky

    The latest ENDF/B nuclear data library released in 2018 is the result of a new international approach to develop evaluated nuclear data for general purpose applications. In order to use the latest ENDF/B-VIII.0 nuclear data library in safety analyses, validation calculations for available benchmark experiments and comparison calculations for previous library versions are required. Validation of this new library for three important reactor areas, criticality safety, fuel depletion and reactor dosimetry, was performed with MCNP6, KENO-VI and Serpent 2 codes for VVER application. Criticality safety and fuel depletion results show better agreement with ICSBEP and SFCOMPO benchmark database cases for the ENDF/B-VIII.0 library when compared with previous libraries including ENDF/B-VII.1. On the other hand, using the latest VIII.0 library for VVER reactor dosimetry applications including neutron fluence on reactor pressure vessel and ex-vessel neutron fluence activation monitors is not recommended since the library gives significantly lower neutron fluence and detector activities when comparing to number of alternative nuclear data libraries. Two nuclides that are dominantly responsible for the discrepancies between the latest ENDF/B library and other libraries were identified as O-16 and Fe-56. The conclusions are limited to VVER application where the water gap between the reactor core and the pressure vessel is significantly decreased compared to PWR.

Klasifikace

  • Druh

    J<sub>imp</sub> - Článek v periodiku v databázi Web of Science

  • CEP obor

  • OECD FORD obor

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

Návaznosti výsledku

  • Projekt

    <a href="/cs/project/TE01020455" target="_blank" >TE01020455: Centrum pokročilých jaderných technologií (CANUT)</a><br>

  • Návaznosti

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

Ostatní

  • Rok uplatnění

    2020

  • Kód důvěrnosti údajů

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

Údaje specifické pro druh výsledku

  • Název periodika

    ANNALS OF NUCLEAR ENERGY

  • ISSN

    0306-4549

  • e-ISSN

  • Svazek periodika

    148

  • Číslo periodika v rámci svazku

    December 2020

  • Stát vydavatele periodika

    GB - Spojené království Velké Británie a Severního Irska

  • Počet stran výsledku

    12

  • Strana od-do

    1-12

  • Kód UT WoS článku

    000568756900041

  • EID výsledku v databázi Scopus

    2-s2.0-85088902403