Author:
Publisher:
ISBN:
Category : Steam power plants
Languages : en
Pages : 146
Book Description
Steam-cooled Power Reactor Evaluation for 300 Mw(e) Separate Superheater Reactor
Steam-cooled Power Reactor Evaluation
Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 266
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 266
Book Description
Steam-cooled Power Reactor Evaluation
Author: G. A. Sofer
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 76
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 76
Book Description
An Evaluation of Reactor Concepts for Use as Separate Steam Superheaters
Author: D. H. Lennox
Publisher:
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.
Publisher:
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.
Power Reactor Technology and Reactor Fuel Processing
Atomic Energy Research Reports for Sale by the U.S. Department of Commerce, Office of Technical Services
Author: Business and Defense Services Administration
Publisher:
ISBN:
Category :
Languages : en
Pages : 68
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 68
Book Description
Power Reactor Technology
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1244
Book Description
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1244
Book Description