The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F16%3A43928598" target="_blank" >RIV/49777513:23220/16:43928598 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21220/16:00310228

Výsledek na webu

<a href="http://www.sciencedirect.com/science/article/pii/S0149197016300555" target="_blank" >http://www.sciencedirect.com/science/article/pii/S0149197016300555</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.pnucene.2016.03.010" target="_blank" >10.1016/j.pnucene.2016.03.010</a>

Jazyk výsledku

angličtina

Název v původním jazyce

The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle

Popis výsledku v původním jazyce

A computer code (UWB1) that is applicable for both light and heavy water reactor fuel types is being developed at the University of West Bohemia. CANDU fuel geometry was investigated in this paper. Fuel depletion with UWB1 code was performed and compared to other depletion codes. A feasibility study on the use of burnable absorbers in CANDU to improve operating margins was recently published [1]. The use of slight enriched fuel (SEU) with various burnable absorbers in CANDU has also been considered for future fuel designs. UWB1 is a fast-calculating depletion code. It is being tested and compared extensively to other six different calculation codes, which include both deterministic and probabilistic types. Although the work focuses primarily on the progress of the multiplication factor during fuel depletion, fuel inventory details were also considered. Effective cross sections as the derivation of reaction rates that directly influence Bateman burnup equations were also compared. Further improvement on the UWB1 code is ongoing. The results showed that UWB1 nuclear fuel depletion code is capable to calculate fuel depletion of CANDU fuel bundle with and without burnable absorbers. As expected, the accuracy of the UWB1 code is lower than the other codes. This paper recommends that UWB1 code be considered as a tool for supporting fuel design assessment, since discrepancies are comparable and the code is one to two orders of magnitude faster than other depletion codes.

Název v anglickém jazyce

The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle

Popis výsledku anglicky

A computer code (UWB1) that is applicable for both light and heavy water reactor fuel types is being developed at the University of West Bohemia. CANDU fuel geometry was investigated in this paper. Fuel depletion with UWB1 code was performed and compared to other depletion codes. A feasibility study on the use of burnable absorbers in CANDU to improve operating margins was recently published [1]. The use of slight enriched fuel (SEU) with various burnable absorbers in CANDU has also been considered for future fuel designs. UWB1 is a fast-calculating depletion code. It is being tested and compared extensively to other six different calculation codes, which include both deterministic and probabilistic types. Although the work focuses primarily on the progress of the multiplication factor during fuel depletion, fuel inventory details were also considered. Effective cross sections as the derivation of reaction rates that directly influence Bateman burnup equations were also compared. Further improvement on the UWB1 code is ongoing. The results showed that UWB1 nuclear fuel depletion code is capable to calculate fuel depletion of CANDU fuel bundle with and without burnable absorbers. As expected, the accuracy of the UWB1 code is lower than the other codes. This paper recommends that UWB1 code be considered as a tool for supporting fuel design assessment, since discrepancies are comparable and the code is one to two orders of magnitude faster than other depletion codes.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JF - Jaderná energetika

OECD FORD obor

—

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)

Rok uplatnění

2016

Kód důvěrnosti údajů

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

Název periodika

Progress in Nuclear Energy

ISSN

0149-1970

e-ISSN

—

Svazek periodika

90

Číslo periodika v rámci svazku

July

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

13

Strana od-do

127-139

Kód UT WoS článku

000376807000012

EID výsledku v databázi Scopus

2-s2.0-84961665320