Published November 1986 | Version v1
Journal article

IVV-2M fuel assembly

Description

A design of an improved fuel assembly (FA) of the IVV-2 water cooled and moderated research reactor is described. The results of neutron-physical, thermal hydraulic and post-reactor studies of fuel assemblies are presented. The FA consists of five hollow three-layer hexagonal fuel elements with cermet fuel (uranium dioxide dispersed in an aluminium matrix). An aluminium alloy is used for the fuel can. In view of the change-over to the new FA the IVV-2M reactor power has increased 1.5 times (up to 15 MW), that has considerably widened its experimental potentialities. The maximum therma neutron flux density has reached 5x1014 cm-2 x s-1

Additional details

Additional titles

Subtitle (English)
Design and experience of application
Original title (Russian)
Тепловыделяющая сборка IVV-2M
Original subtitle (Russian)
Razrabotka i opyt ispol'zovaniya.

Publishing Information

Journal Title
At. Ehnerg.
Journal Volume
61
Journal Issue
5
Series
At. Ehnerg.
Journal Page Range
344-346
ISSN
0004-7163
CODEN
AENGA