Published 1996 | Version v1
Book

To the application of hypostoichiometric uranium dioxide in space power reactors

Description

The advantages of applying the uranium dioxide of pre-stoichiometric composition in fuel elements of thermo-emission reactors-inventor are considered. The results of experiments on obtaining the pre-stoichiometric dioxide are presented in ready-made products. Batches of the UO1.975 fuel pellets are manufactured by annealing at 1750 ± 10 deg C and sealed container in the presence of the tantalum getter

Abstract (Russian)

Расмотрены преимущества использования в твэлах термоэмиссионных реакторов-преобразователей диоксида урана достехиометрического состава. Приведены результаты экспериментов по получению достехиометрического диоксида в готовых изделиях. Отжигом при температуре 1750 ± 10 град. С в герметичном контейнере в присутствии танталового геттера получены партии таблеток состава UO1,975
Part of:
Collection of reports of the 4. Inter-industry conference on reactor materials. Volume 1. Fuel and fuel elements for power reactors

Additional details

Additional titles

Original title (Russian)
К вопросу о применении достехиометрического диоксида урана в реакторах космического назначения

Publishing Information

Publisher
GNTs RF NIIAR
Imprint Place
Dimitrovgrad (Russian Federation)
ISBN
5-85165-169-5
Imprint Title
Collection of reports of the 4. Inter-industry conference on reactor materials. Volume 1. Fuel and fuel elements for power reactors
Imprint Pagination
431 p.
Journal Page Range
p. 246-249

Conference

Title
4. Inter-industry conference on reactor materials
Original Conference Title
4. Mezhotraslevaya konferentsiya po reaktornomu materialovedeniyu
Dates
15-19 May 1995
Place
Dimitrovgrad (Russian Federation)

Optional Information

Notes
6 refs. Imprint:Sbornik dokladov 4. Mezhotraslevoj konferentsii po reaktornomu materialovedeniyu. Tom 1. Toplivo i tvehly ehnergeticheskikh reaktorov