Published 1999 | Version v1
Miscellaneous Metadata-only

Studying the behaviour of mockups of fuel elements with oxide fuel in Pb-Bi coolant under emergency superheating s

Creators

  • 1. GNTs RF FEhI, Obninsk (Russian Federation)

Description

The results of studying the behavior of the fuel elements with the UO2-fuel in the Pb-Bi eutectic melt under the conditions of the hypothetical emergency accident are presented. It is shown that interaction of the fuel element shell ferrite steel with the Pb-Bi-melt is of no throughout character. The conclusion is made on the high reliability of the selected fuel element design under emergency conditions

Abstract (Russian)

Приведены результаты исследований поведения твэлов с UO2-топливом в Pb-Bi эвтектическом сплаве в условиях протекания гипотетической тяжелой аварии. Показано, что коррозионное взаимодействие ферритной стали оболочки твэла с Pb-Bi сплавом не носит сквозного характера. Сделан вывод о высокой надежности выбранной конструкции твэла в экстремальных условиях
Part of:
Heavy liquid-metal coolants in the nuclear technologies. Collection of reports of the conference in two volumes. Volume 2

Additional details

Additional titles

Original title (Russian)
Исследование поведения макетов твэлов с оксидным топливом в свинцово-висмутовом теплоносителе при аварийных перегревах

Publishing Information

Publisher
GNTs RF FEhI
Imprint Place
Obninsk (Russian Federation)
Imprint Title
Heavy liquid-metal coolants in the nuclear technologies. Collection of reports of the conference in two volumes. Volume 2
Imprint Pagination
824 p.
Journal Page Range
p. 765-766
Report number
INIS-RU--475

Conference

Title
Heavy liquid-metal coolants in the nuclear technologies
Original Conference Title
Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh
Dates
5-9 Oct 1998
Place
Obninsk (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
34075955
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BISMUTH; CLADDING; CORROSION; EUTECTICS; FERRITIC STEELS; FUEL ELEMENTS; FUEL-COOLANT INTERACTIONS; LEAD; MOCKUP; RELIABILITY; RISK ASSESSMENT; SUPERHEATING; THERMAL TESTING; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL REACTIONS; DEPOSITION; ELEMENTS; HEATING; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; METALS; NONDESTRUCTIVE TESTING; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; STEELS; STRUCTURAL MODELS; SURFACE COATING; TESTING; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
1 fig. Imprint:Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh. Sbornik dokladov konferentsii v 2-kh tomakh. Tom 2