Author: D. B. Hall
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 134
Book Description
A Preliminary Study of a Fast Reactor Core Test Facility
Author: D. B. Hall
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 134
Book Description
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 134
Book Description
Fast Reactor Core Test Facility Safety Analysis Report
Author: Los Alamos Scientific Laboratory. K Division
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 160
Book Description
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 160
Book Description
FAST REACTOR TEST FACILITY (FARET). VOLUME II. SUMMARY OF PRELIMINARY SAFETY ANALYSIS.
Nuclear Science Abstracts
An Engineering Test Reactor for the MTR Site
Author: R. M. Jones
Publisher:
ISBN:
Category : Engineering test reactors
Languages : en
Pages : 78
Book Description
Publisher:
ISBN:
Category : Engineering test reactors
Languages : en
Pages : 78
Book Description
Power Reactor Designs
Reactor Technology
Author: Leonard E. Link
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 636
Book Description
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 636
Book Description
U.S. Government Research Reports
Power Reactor Technology
Ultra High Temperature Reactor Experiment (UHTREX) Hazard Report
Author: Los Alamos Scientific Laboratory. K-Division
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 168
Book Description
UHTREX utilizes a high-temperature, He-cooled, graphite moderated reactor employing unclad, refractory fuel elements. The reactor is designed to produce a maximum thermal power of 3 Mw and a maximum exit He temperature of 2400 deg F. The purpose of the experimert is to evaluate the advantages of the simple fuel against the disadvantages of the associated operation of a contaminated coolant loop. The mechanical and nuclear design of the reactor and related apparatus are described, discussed, and evaluated from the standpoint of hazards associated with conduct of the experiment. The building design and characteristics of the site are also examined from the same standpoint. The probable effects of operational errors and component failures are studied. The conseqnences of credible accidents are not considered to be catastrophic for either operating personnel or personnel in surrounding areas.
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 168
Book Description
UHTREX utilizes a high-temperature, He-cooled, graphite moderated reactor employing unclad, refractory fuel elements. The reactor is designed to produce a maximum thermal power of 3 Mw and a maximum exit He temperature of 2400 deg F. The purpose of the experimert is to evaluate the advantages of the simple fuel against the disadvantages of the associated operation of a contaminated coolant loop. The mechanical and nuclear design of the reactor and related apparatus are described, discussed, and evaluated from the standpoint of hazards associated with conduct of the experiment. The building design and characteristics of the site are also examined from the same standpoint. The probable effects of operational errors and component failures are studied. The conseqnences of credible accidents are not considered to be catastrophic for either operating personnel or personnel in surrounding areas.