Possibility of implementation of 6-year fuel cycle at NPP with VVER-440 reactor
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F15%3A00237186" target="_blank" >RIV/68407700:21340/15:00237186 - isvavai.cz</a>
Alternative codes found
RIV/46356088:_____/15:#0001710
Result on the web
<a href="http://dx.doi.org/10.1016/j.nucengdes.2015.08.024" target="_blank" >http://dx.doi.org/10.1016/j.nucengdes.2015.08.024</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.nucengdes.2015.08.024" target="_blank" >10.1016/j.nucengdes.2015.08.024</a>
Alternative languages
Result language
angličtina
Original language name
Possibility of implementation of 6-year fuel cycle at NPP with VVER-440 reactor
Original language description
This paper discusses possibility of an extension of a fuel cycle at a VVER-440 reactor for up to 6 years. The prolongation of a fuel cycle was realized by optimization of a fuel design and increasing of a fuel enrichment. The modified design of the fuelassembly covers change of pellet geometry, decreasing of parasitic absorption in construction materials, improved moderation of fuel pins and also increase of enrichment. Fuel assemblies with enrichment up to 7% U-235 are considered for prolonged fuel batches. Three different batch lengths were considered for evaluation of core properties - 12,18 and 24 months, and two types of burnable absorbers were included - Gd2O3 and Er2O3. Comparison of proposed fuel assemblies was realized by length of a batch, average burnup, maximal power of fuel assembly or fuel pin, control fuel assembly worth, reactivity coefficients, and effective delayed neutrons fraction. Comparison of characteristics of a burned fuel discharged from a reactor core is dis
Czech name
—
Czech description
—
Classification
Type
J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP classification
JF - Nuclear energy
OECD FORD branch
—
Result continuities
Project
<a href="/en/project/TE01020455" target="_blank" >TE01020455: Centre for Advanced Nuclear Technologies (CANUT)</a><br>
Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2015
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Nuclear Engineering and Design
ISSN
0029-5493
e-ISSN
—
Volume of the periodical
295
Issue of the periodical within the volume
Dec
Country of publishing house
NL - THE KINGDOM OF THE NETHERLANDS
Number of pages
8
Pages from-to
40-47
UT code for WoS article
000367413700004
EID of the result in the Scopus database
2-s2.0-84945179250