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DIFFUSION OF BARIUM, STRONTIUM AND CERIUM IN VARIOUS GRADES OF REACTOR GRAPHITE. Project DRAGON.

Technical Report ·
OSTI ID:4110225
; ;
A knowledge of the rate and mechanism of the migration of metallic fission products through graphite is of importance in the design of high temperature reactor systems, such as Dragon, where graphite is used for fission product containment. This paper describes an investigation, carried out as part of the Dragon Reactor Experiment Basic Research Programme, on the diffusion of barium, strontium and cerium through various grades of graphite of particular interest to Dragon.
Research Organization:
Atomic Energy Research Establishment, Harwell (England)
NSA Number:
NSA-24-039701
OSTI ID:
4110225
Report Number(s):
DP-Report--358; AERE-R--4994
Country of Publication:
United Kingdom
Language:
English

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Related Subjects

BARIUM
BARIUM/diffusion in reactor-grade graphite
CERIUM
CERIUM/diffusion in reactor-grade graphite
DIFFUSION
GRAPHITE
GRAPHITE/diffusion of barium, cerium, and strontium in reactor-grade
N30230* --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Properties Evaluations
STRONTIUM
STRONTIUM/diffusion in reactor-grade graphite