Author: M. A. Salmon
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 110
Book Description
Effects of Tube Leaks in Sodium-heated Steam Generators
Author: M. A. Salmon
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 110
Book Description
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 110
Book Description
ASME 69-WA/NE-18
Author: Thomas Allen Zaker
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages : 7
Book Description
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages : 7
Book Description
Sodium-Heated Steam Generator Development. Interim Status Report
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Design and development of a once -through sodiumheated steam generator are discussed. Research proposals are discussed for evaluating: carbon transfer and mass transfer effects in the steam generator, effect on heat transfer and two- phase flow of coiling tubes, corrosion of Croloy 21/4 in products of sodium-water reactions, procedure for welding tube to back side of the tube sheet, radiographic inspection of back side tube welds, and chemical simulation of sodium environment for leak testing. (N.W.R.).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Design and development of a once -through sodiumheated steam generator are discussed. Research proposals are discussed for evaluating: carbon transfer and mass transfer effects in the steam generator, effect on heat transfer and two- phase flow of coiling tubes, corrosion of Croloy 21/4 in products of sodium-water reactions, procedure for welding tube to back side of the tube sheet, radiographic inspection of back side tube welds, and chemical simulation of sodium environment for leak testing. (N.W.R.).
Nuclear Science Abstracts
TID.
Nuclear Power Reactor Instrumentation Systems Handbook
Author: Joseph M. Harrer
Publisher:
ISBN: 9780870790058
Category : Technology & Engineering
Languages : en
Pages : 1052
Book Description
Publisher:
ISBN: 9780870790058
Category : Technology & Engineering
Languages : en
Pages : 1052
Book Description
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages : 776
Book Description
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages : 776
Book Description
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration. Technical Information Center
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 1066
Book Description
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 1066
Book Description
Energy Research Abstracts
Analysis of Long-term Flows Resulting from Large-scale Sodium-water Reactions in an LMFBR Secondary System
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Leaks in LMFBR steam generators cannot entirely be prevented; thus the steam generators and the intermediate heat transport system (IHTS) of an LMFBR must be designed to withstand the effects of the leaks. A large-scale leak which might result from a sudden break of a steam generator tube, and the resulting sodium-water reaction (SWR) can generate large pressure pulses that propagate through the IHTS and exert large forces on the piping supports. This paper discusses computer programs for analyzing long-term flow and thermal effects in an LMFBR secondary system resulting from large-scale steam generator leaks, and the status of the development of the codes.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Leaks in LMFBR steam generators cannot entirely be prevented; thus the steam generators and the intermediate heat transport system (IHTS) of an LMFBR must be designed to withstand the effects of the leaks. A large-scale leak which might result from a sudden break of a steam generator tube, and the resulting sodium-water reaction (SWR) can generate large pressure pulses that propagate through the IHTS and exert large forces on the piping supports. This paper discusses computer programs for analyzing long-term flow and thermal effects in an LMFBR secondary system resulting from large-scale steam generator leaks, and the status of the development of the codes.