A Preliminary Study of a Fast Reactor Core Test Facility PDF Download

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A Preliminary Study of a Fast Reactor Core Test Facility

A Preliminary Study of a Fast Reactor Core Test Facility PDF 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

A Preliminary Study of a Fast Reactor Core Test Facility PDF Author: D. B. Hall
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 134

Book Description


Fast Reactor Core Test Facility Safety Analysis Report

Fast Reactor Core Test Facility Safety Analysis Report PDF Author: Los Alamos Scientific Laboratory. K Division
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 160

Book Description


FAST REACTOR TEST FACILITY (FARET). VOLUME II. SUMMARY OF PRELIMINARY SAFETY ANALYSIS.

FAST REACTOR TEST FACILITY (FARET). VOLUME II. SUMMARY OF PRELIMINARY SAFETY ANALYSIS. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 920

Book Description


An Engineering Test Reactor for the MTR Site

An Engineering Test Reactor for the MTR Site PDF Author: R. M. Jones
Publisher:
ISBN:
Category : Engineering test reactors
Languages : en
Pages : 78

Book Description


Power Reactor Designs

Power Reactor Designs PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 550

Book Description


Reactor Technology

Reactor Technology PDF Author: Leonard E. Link
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 636

Book Description


U.S. Government Research Reports

U.S. Government Research Reports PDF Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 140

Book Description


Power Reactor Technology

Power Reactor Technology PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 888

Book Description


Ultra High Temperature Reactor Experiment (UHTREX) Hazard Report

Ultra High Temperature Reactor Experiment (UHTREX) Hazard Report PDF 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.