Development of high thermal conductivity UO2–Th heterogeneous fuel

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F18%3A00322264" target="_blank" >RIV/68407700:21220/18:00322264 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/18:00322264 RIV/68407700:21730/18:00322264

Výsledek na webu

<a href="https://www-sciencedirect-com.libproxy.mit.edu/science/article/pii/S0149197018301604?via%3Dihub" target="_blank" >https://www-sciencedirect-com.libproxy.mit.edu/science/article/pii/S0149197018301604?via%3Dihub</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.pnucene.2018.06.012" target="_blank" >10.1016/j.pnucene.2018.06.012</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Development of high thermal conductivity UO2–Th heterogeneous fuel

Popis výsledku v původním jazyce

A novel design of heterogeneous UO2–Th nuclear fuel for light water reactors (LWRs) is proposed. The main advantages of the design are higher thermal conductivity, reduced maximal temperature in the fuel, lower heat stored in the fuel system, or higher thermal breeding ratio. Thermal, neutronics and simple economics calculations were performed to determine the benefits of the new fuel concept. Moreover, an experimental setup utilizing flashing method for measuring of thermal characteristics was designed. It will serve to confirm theoretical assumptions and to precisely determine thermal conductivity and heat capacity of the proposed fuel design and to assess thermal resistance between pellets and Th plates. The many substantial benefits of the proposed fuel design are reached with very competitive cost, which is also estimated.

Název v anglickém jazyce

Development of high thermal conductivity UO2–Th heterogeneous fuel

Popis výsledku anglicky

A novel design of heterogeneous UO2–Th nuclear fuel for light water reactors (LWRs) is proposed. The main advantages of the design are higher thermal conductivity, reduced maximal temperature in the fuel, lower heat stored in the fuel system, or higher thermal breeding ratio. Thermal, neutronics and simple economics calculations were performed to determine the benefits of the new fuel concept. Moreover, an experimental setup utilizing flashing method for measuring of thermal characteristics was designed. It will serve to confirm theoretical assumptions and to precisely determine thermal conductivity and heat capacity of the proposed fuel design and to assess thermal resistance between pellets and Th plates. The many substantial benefits of the proposed fuel design are reached with very competitive cost, which is also estimated.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10304 - Nuclear physics

Projekt

—

Návaznosti

S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2018

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

108

Číslo periodika v rámci svazku

September

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

8

Strana od-do

489-496

Kód UT WoS článku

000442979400050

EID výsledku v databázi Scopus

2-s2.0-85049575525