Benchmarking of fission and activation rate in VVER-1000 mock-up in LR-0 reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000068" target="_blank" >RIV/26722445:_____/16:N0000068 - isvavai.cz</a>

Výsledek na webu

—

DOI - Digital Object Identifier

—

Jazyk výsledku

angličtina

Název v původním jazyce

Benchmarking of fission and activation rate in VVER-1000 mock-up in LR-0 reactor

Popis výsledku v původním jazyce

The VVER-1000 core and vessel radial mockup was developed for reactor core studies. This device was used for benchmark experiments including neutron transport and fission density measurements in different positions, which can be problematic for diffusion codes used in full core modeling. The comparison of statistic MCNP6.1 code with ENDF/B-VII.O library and code MOBY DICK used by Czech utilities is shown. The fission densities have been determined by means of gamma activity of selected fission products. 92Sr is one of the short-living products with convenient gamma lines however this measurement was supplemented by midterm-living 140La as well. Activation foils containing 197Au were employed for neutron flux measurement in non-fissile regions of the mock-up. It can be concluded, based on provided results, that the diffusion model of the fuel-reflector boundary in MOBY DICK code is within 3 sigma uncertainty interval, but the results are systematically overestimated in case of 92Sr activity. Satisfactory agreement has been determined also for results of 140La, but special treatment is required for absolute evaluation. Thermal fluxes in cooling channels located in the baffle body and measured by means of activation analysis are in good agreement with MCNP6.1 calculations, although some variations in smaller channels were observed.

Název v anglickém jazyce

Benchmarking of fission and activation rate in VVER-1000 mock-up in LR-0 reactor

Popis výsledku anglicky

The VVER-1000 core and vessel radial mockup was developed for reactor core studies. This device was used for benchmark experiments including neutron transport and fission density measurements in different positions, which can be problematic for diffusion codes used in full core modeling. The comparison of statistic MCNP6.1 code with ENDF/B-VII.O library and code MOBY DICK used by Czech utilities is shown. The fission densities have been determined by means of gamma activity of selected fission products. 92Sr is one of the short-living products with convenient gamma lines however this measurement was supplemented by midterm-living 140La as well. Activation foils containing 197Au were employed for neutron flux measurement in non-fissile regions of the mock-up. It can be concluded, based on provided results, that the diffusion model of the fuel-reflector boundary in MOBY DICK code is within 3 sigma uncertainty interval, but the results are systematically overestimated in case of 92Sr activity. Satisfactory agreement has been determined also for results of 140La, but special treatment is required for absolute evaluation. Thermal fluxes in cooling channels located in the baffle body and measured by means of activation analysis are in good agreement with MCNP6.1 calculations, although some variations in smaller channels were observed.

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

—

Projekt

<a href="/cs/project/ED2.1.00%2F03.0108" target="_blank" >ED2.1.00/03.0108: Udržitelná energetika</a><br>

Návaznosti

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

Rok uplatnění

2016

Kód důvěrnosti údajů

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

Název statě ve sborníku

Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century Volume 4, 2016

ISBN

978-1-5108-2573-4

ISSN

—

e-ISSN

—

Počet stran výsledku

13

Strana od-do

2548-2560

Název nakladatele

American Nuclear Society

Místo vydání

Red Hook, NY, USA

Místo konání akce

Sun Valley, Idaho, USA

Datum konání akce

1. 5. 2016

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

—