Maritime Nuclear Steam Generator Progress Report No. 4 PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Maritime Nuclear Steam Generator Progress Report No. 4 PDF full book. Access full book title Maritime Nuclear Steam Generator Progress Report No. 4 by General Electric Company. Nuclear Materials and Propulsion Operation. Download full books in PDF and EPUB format.
Author: General Electric Company. Nuclear Materials and Propulsion Operation
Publisher:
ISBN:
Category : Propulsion systems
Languages : en
Pages : 142
Get Book Here
Book Description
Author: General Electric Company. Nuclear Materials and Propulsion Operation
Publisher:
ISBN:
Category : Propulsion systems
Languages : en
Pages : 142
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
A layout of a reduced-height 630A assembly (34 to 23 ft) was prepared and is presently being evaluated for use in a merchant vessel. While shielding studies indicate the need for some rearrangement of the shield materials, the desired radiation constraint can be obtained without an increase in shielding weight. A preliminary stress analysis of the pressure vessel, flow path analysis, and insulation evaluation was completed and showed no major problems. Evaluation of the total containment design indicates a design pressure of 45 psig. The Critical Experiment (CE) mockup is about 80% complete. The CE tank and dolly is about 50% complete. The CE hazards report was reviewed and approved. The draft of the test program and procedures document is 75% complete. The LPT control room modifications were made, and the draft of the standard operating procedures completed. The CE fuel was inspected and a significant portion was found to be of no use, about 60% requires recoating. Creep and oxidation test time on some of the fuel sheet has exceeded 3000 hr with no significant oxidation or elongation on any of the samples. The nickel -chromium alloy sheet high- temperature (1750 F) stress and oxidating testing have exceeded 5000 hr with elongations below 0.8% except for one sample of 2.3%. Experimental fuel sheet samples were prepared and comparative property studies were ini-tiated. Fabrication of the ring test assembly, 3-F-1, for test in the MTR is essentially complete. The design of the test ring for seal evaluations was initiated. A detailed schedule for the work in FY 63 was prepared and issued for comments and concurrence. (auth).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Marine nuclear reactor plants
Languages : en
Pages : 284
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
The current status of the 630A nuclear steam generator program is given. Information is included on the propulsion system, reactor, shield plus, pressure vessel, boiler, controls, primary coolant system, associated test equipment, auxiliary cooling system, critical experiment test operations, handling equipment, facilities and equipment, fuel materials, and safety analysis. (N.W.R.).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 119
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
Author: General Electric Company
Publisher:
ISBN:
Category : Marine nuclear reactor plants
Languages : en
Pages : 96
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
A summary of the progress made on the 630 A Maritime Nuclear Steam Generator is preserted. Information is included on propulsion system investigations, reactor design, side shield development, boiler design, containment development, development of controls, development of primary coolant blowers, development of fuel materials, development of nonfuel materials, critical experiments, safety analyses, and development of facilities and equipment. (J.R.D.).
