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