Possibility of implementation of 6-year fuel cycle at NPP with VVER-440 reactor

Kód výsledku v 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>

Nalezeny alternativní kódy

RIV/46356088:_____/15:#0001710

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

Possibility of implementation of 6-year fuel cycle at NPP with VVER-440 reactor

Popis výsledku v původním jazyce

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

Název v anglickém jazyce

Possibility of implementation of 6-year fuel cycle at NPP with VVER-440 reactor

Popis výsledku anglicky

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

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

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2015

Kód důvěrnosti údajů

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

Název periodika

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

—

Svazek periodika

295

Číslo periodika v rámci svazku

Dec

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

8

Strana od-do

40-47

Kód UT WoS článku

000367413700004

EID výsledku v databázi Scopus

2-s2.0-84945179250