Deterministic and Stochastic Neutron Cross-section Generation for PARCS Applied to VR-1 Reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F16%3A00302690" target="_blank" >RIV/68407700:21340/16:00302690 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1109/EPE.2016.7521770" target="_blank" >http://dx.doi.org/10.1109/EPE.2016.7521770</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1109/EPE.2016.7521770" target="_blank" >10.1109/EPE.2016.7521770</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Deterministic and Stochastic Neutron Cross-section Generation for PARCS Applied to VR-1 Reactor

Popis výsledku v původním jazyce

The VR-1 reactor operated by the Czech Technical University in Prague was utilized for a study of a macroscopic cross-sections homogenization performed by deterministic (SCALE 6.1.2-Triton) and stochastic (Serpent 2.1.24) codes. These cross-sections are subsequently imported into a fixed source problem solved by the three-dimensional reactor core simulator PARCS v3.2. PARCS solves the steady-state and time-dependent, multi-group neutron diffusion and low order transport equations. All multiplication factors provided by each code are compared and discussed. Due to the small size of the core, all elements are more closely coupled by neutron fluxes in surrounding positions; therefore homogenization must be conducted in properly chosen volumes to respect all effects of a spatiality.

Název v anglickém jazyce

Deterministic and Stochastic Neutron Cross-section Generation for PARCS Applied to VR-1 Reactor

Popis výsledku anglicky

The VR-1 reactor operated by the Czech Technical University in Prague was utilized for a study of a macroscopic cross-sections homogenization performed by deterministic (SCALE 6.1.2-Triton) and stochastic (Serpent 2.1.24) codes. These cross-sections are subsequently imported into a fixed source problem solved by the three-dimensional reactor core simulator PARCS v3.2. PARCS solves the steady-state and time-dependent, multi-group neutron diffusion and low order transport equations. All multiplication factors provided by each code are compared and discussed. Due to the small size of the core, all elements are more closely coupled by neutron fluxes in surrounding positions; therefore homogenization must be conducted in properly chosen volumes to respect all effects of a spatiality.

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

—

Projekt

—

Návaznosti

S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2016

Kód důvěrnosti údajů

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

Název statě ve sborníku

2016 17th International Scientific Conference on Electric Power Engineering (EPE 2016)

ISBN

978-1-5090-0907-7

ISSN

2376-5623

e-ISSN

—

Počet stran výsledku

4

Strana od-do

548-551

Název nakladatele

IEEE

Místo vydání

New York

Místo konání akce

Praha

Datum konání akce

16. 5. 2016

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

000382934600056