Published 2006 | Version v1
Book Metadata-only

Capillary impregnation technology for novel types of fuels

Creators

  • 1. A.A. Bochvar All-Russian Scientific Research Institute of Inorganic Materials, 123060 Moscow (Russian Federation)

Description

Novel dispersion fuel compositions with high uranium content fuel (U9Mo, U5Zr5Nb, U3Si) and a matrix based on a low melting point (690-860 °C) zirconium alloys as well as method of their fabrication by capillary impregnation have been developed at A.A. Bochvar Institute. Capillary impregnation method involves introducing fuel granules along with granules of zirconium matrix alloy into a fuel element followed by a short-term anneal at temperature above the melting temperature of alloy

Part of:
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.1

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.1
Imprint Pagination
179 p.
Journal Page Range
p. 22

Conference

Title
international conference on advances in nuclear materials processing, performance and phenomena; MBFE 2006: satellite conference on materials behaviour- far from equilibrium
Acronym
ANM 2006
Dates
12-16 Dec 2006
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
50063907
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CANDU TYPE REACTORS; FUEL ELEMENTS; MELTING POINTS; REACTOR MATERIALS; URANIUM; URANIUM RECYCLE; URANIUM-MOLYBDENUM FUELS
Descriptors DEC
ACTINIDES; ALLOY NUCLEAR FUELS; CLOSED FUEL CYCLE; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL CYCLE; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; METALS; NUCLEAR FUELS; PHYSICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION TEMPERATURE; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
This record replaces 50063127