Author: H. L. FalkenberryPublisher:
ISBN:
Category : Nuclear reactions
Languages : en
Pages : 28
Book Description
A Preliminary Study of a Direct-cycle Steam-cooled Reactor for Merchant Ship Propulsion
Author: H. L. FalkenberryPublisher:
ISBN:
Category : Nuclear reactions
Languages : en
Pages : 28
Book Description
Preliminary Design
Author: Publisher:
ISBN:
Category : Nuclear merchant ships
Languages : en
Pages : 252
Book Description
Nuclear Science Abstracts
Author: Gas-cooled Reactor Project Semiannual Progress Report for Period Ending ...
Author: Oak Ridge National LaboratoryPublisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 238
Book Description
Nuclear Science Abstracts
Author: U.S. Government Research Reports
Author: Investigation of Wet Steam as a Reactor Coolant (CAN-2): Conceptual design evaluation of a fog-cooled light water reactor (Volume 2, Final Report)
Author: Power Reactor Technology
Author: Study of Steam Power Cycle and Equipment for the Pilot Model Homogeneous Reactor Experiment and Preliminary Study of Steam Power Cycle for a Full Scale Homogeneous Reactor
Author: Roy C. RobertsonPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 92
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.