Author: Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 90
Book Description
Steam-cooled Power-reactor Evaluation
Author: Steam-cooled Power Reactor Evaluation
Author: G. A. SoferPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 76
Book Description
Heavy-water-moderated Power Reactors Engineering and Economic Evaluations
Author: E.I. du Pont de Nemours & Company. Engineering Department. Design DivisionPublisher:
ISBN:
Category : Heavy water reactors
Languages : en
Pages : 124
Book Description
Power Reactor Technology
Author: Nuclear Science Abstracts
Author: Monthly Catalog of United States Government Publications
Author: Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1878
Book Description
Status of the United States Effort in D2O Reactor Physics
Author: John L. CrandallPublisher:
ISBN:
Category : Deuterium oxide
Languages : en
Pages : 98
Book Description
Bibliographical Series
Author: International Atomic Energy AgencyPublisher:
ISBN:
Category :
Languages : en
Pages : 1036
Book Description
Atomic Energy Research Reports for Sale by the U.S. Department of Commerce, Office of Technical Services
Author: Business and Defense Services AdministrationPublisher:
ISBN:
Category :
Languages : en
Pages : 68
Book Description
An Evaluation of Reactor Concepts for Use as Separate Steam Superheaters
Author: D. H. LennoxPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 78
Book Description
Various reactor concepts were compared for use as a separate superheater which could be added on to an advanced 300-Mwe reactor producing saturated steam. Fossil steam plant superheat temperatures were used as a criterion for selecting nuclear superheat temperatures. Therefore, the performance specified for the superheater was a minimum exit steam temperature of 566 deg C (1050 deg F) when supplied with saturated steam at either 71 atm (1050 psia) or 167 atm (2450 psia). A preliminary screening of ten different reactor concepts resulted in the selection of two for a detailed evaluation. These are a direct-cycle, water-moderated reactor, and an indirect-cycle, sodium-cooled reactor. The steam- cooled, water-moderated system is judged to have the best chance for initially reaching 566 deg C (l050 deg F), whereas, the indirect-cycle, sodium-cooled system is considered best for subsequent advances to exploit the more efficient, high- pressure steam reheat cycles. A design concept was selected for each of the reactors to establish a basis for the detailed evaluations and comparisons.