z-logo
open-access-imgOpen Access
COMPARISON OF TWO TRITIUM REMOVAL SYSTEMS DESIGNED TO MINIMIZE CONTAMINATION OF STEAM SYSTEMS IN FULL-SCALE THERMONUCLEAR POWER PLANTS.
Author(s) -
A.P. Fraas
Publication year - 1970
Language(s) - English
Resource type - Reports
DOI - 10.2172/4137247
Subject(s) - blanket , beryllium , nuclear engineering , fusion power , tritium , lithium (medication) , thermonuclear fusion , chemistry , materials science , environmental science , nuclear physics , plasma , engineering , composite material , physics , medicine , organic chemistry , endocrinology

The content you want is available to Zendy users.

Already have an account? Click here to sign in.
Having issues? You can contact us here
Accelerating Research

Address

John Eccles House
Robert Robinson Avenue,
Oxford Science Park, Oxford
OX4 4GP, United Kingdom