Author: W. C. Francis
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
REACTOR FUELS AND MATERIALS DEVELOPMENT. ANNUAL PROGRESS REPORT FOR FY 1966
Annual Progress Report on Reactor Fuels and Materials Development for FY 1967
Annual Progress Report on Reactor Fuels and Materials Development for ...
Author:
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 58
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 58
Book Description
Annual Progress Report on Reactor Fuels and Materials Development for FY 1964
Annual Progress Report on Reactor Fuels and Materials Development for FY 1966
Annual Progress Report on Reactor Fuels and Materials Development for FY 1964
Annual Progress Report on Reactor Fuels and Materials Development for FY 1965
Summaries of Fuels and Materials Development Programs
Author: William L. R. Rice
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 264
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 264
Book Description
Quarterly Progress Report
Quarterly Progress Report January, February, March, 1968 Reactor Fuels and Materials Development Programs for Fuels and Materials Branch of Usaec Division of Reactor Development and Technology
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Progress is reported in these areas: nuclear graphite; fuel development for gas-cooled reactors; HTGR graphite studies; nuclear ceramics; fast-reactor nitrides research; non-destructive testing; metallic fuels; basic swelling studies; ATR gas and water loop operation and maintenance; reactor fuels and materials; fast reactor dosimetry and damage analysis; and irradiation damage to reactor metals.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Progress is reported in these areas: nuclear graphite; fuel development for gas-cooled reactors; HTGR graphite studies; nuclear ceramics; fast-reactor nitrides research; non-destructive testing; metallic fuels; basic swelling studies; ATR gas and water loop operation and maintenance; reactor fuels and materials; fast reactor dosimetry and damage analysis; and irradiation damage to reactor metals.