Author: Publisher:
ISBN:
Category : Fossil fuel power plants
Languages : en
Pages : 626
Book Description
An Evaluation of Fossil Superheat for Nuclear Power Plants
Author: Publisher:
ISBN:
Category : Fossil fuel power plants
Languages : en
Pages : 626
Book Description
Task Force Evaluation Report--smallsized Nuclear Power Plant Program
Author: U.S. Atomic Energy CommissionPublisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 72
Book Description
Superheated Steam in Nuclear Power Plants
Author: Jagjiwan KoshalNuclear Science Abstracts
Author: Steam-cooled Power Reactor Evaluation
Author: Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 266
Book Description
Nuclear Power Economics
Author: Business Service Check List
Author: Atomic Industry Reporter: Technology reports
Author: Bureau of National Affairs (Arlington, Va.)Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1828
Book Description
Nuclear Power Economies; [bibliography].
![Nuclear Power Economies; [bibliography]. PDF](https://books.google.com/books/content/images/frontcover/rF0WAQAAIAAJ?fife=w80-h100)
Author: International Atomic Energy AgencyPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 176
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.