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

Result code in 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>

Alternative codes found

RIV/68407700:21220/16:00310228

Result on the web

<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>

Result language

angličtina

Original language name

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

Original language description

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.

Czech name

—

Czech description

—

Type

J_x - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)

CEP classification

JF - Nuclear energy

OECD FORD branch

—

Project

<a href="/en/project/TE01020455" target="_blank" >TE01020455: Centre for Advanced Nuclear Technologies (CANUT)</a><br>

Continuities

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

Publication year

2016

Confidentiality

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

Name of the periodical

Progress in Nuclear Energy

ISSN

0149-1970

e-ISSN

—

Volume of the periodical

90

Issue of the periodical within the volume

July

Country of publishing house

GB - UNITED KINGDOM

Number of pages

13

Pages from-to

127-139

UT code for WoS article

000376807000012

EID of the result in the Scopus database

2-s2.0-84961665320