Published 1990 | Version v1
Report

Development and testing of UO2-Cr dispersing full for fast reactor application

  • 1. AN Ukrainskoj SSR, Kharkov (Ukraine). Fiziko-Tekhnicheskij Inst.

Description

Data on creation of oxide dispersing fuel with chromium matrix are presented. Operating conditions of UO2-Cr micro fuel element production and their consolidation into fuel cores were worked out. Proposed studies of corrosion resistance of cores in wide temperature range in water, vapour, oxygen, nitrogen gave positive results. Fuel tests in fuel elements of nuclear reactors showed reliable efficiency for fuel elements at deplation more than 10% h.a. 5 refs.; 4 figs.; 3 tabs. (author)

Part of:
Radiation materials science. V. 8

Additional details

Additional titles

Original title (Russian)
Разработка и испытания дисперсионного горючего UO

Publishing Information

Imprint Title
Radiation materials science. V. 8
Imprint Pagination
232 p.
Journal Page Range
p. 103-111.
Report number
INIS-mf--13547

Conference

Title
International conference on radiation materials science.
Original Conference Title
Mezhdunarodnaya konferentsiya po radiatsionnomu materialovedeniyu
Dates
22-25 May 1990.
Place
Alushta (Ukraine).

Optional Information

Notes
Imprint:Radiatsionnoe materialovedenie. Tom 8.