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2 edition of Interim technical report on BWR feedwater and control rod drive return line nozzle cracking found in the catalog.

Interim technical report on BWR feedwater and control rod drive return line nozzle cracking

U.S. Nuclear Regulatory Commission. Division of Operating Reactors

Interim technical report on BWR feedwater and control rod drive return line nozzle cracking

by U.S. Nuclear Regulatory Commission. Division of Operating Reactors

  • 350 Want to read
  • 24 Currently reading

Published by Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Operating Reactors, for sale by the National Technical Information Service in [Washington], Springfield, Va .
Written in English

    Subjects:
  • Boiling water reactors,
  • Nozzles

  • Edition Notes

    Published July 1977

    SeriesNUREG ; 0312, NUREG -- 0312
    The Physical Object
    Pagination[1], iii, 28 p. :
    Number of Pages28
    ID Numbers
    Open LibraryOL14947441M

    (boiling water reactor) plants based on systems developed Replacement for BWR-3/4/5 Hydraulic drive control rod Sequence time drive by manual operation Rod-block, etc. (1) Central control cabinet (replacement) + field cabinet (replacement) This report described a control system for a control rod as part of a next-generation product for BWR. The Dedicated Recirc System converts an existing hot water circulation line into an efficient on-demand delivery system.. The Dedicated Recirc System delivers hot water only when there is a demand. Reducing Energy Costs; Virtually Eliminating Pinhole Leaks; When the Flow Monitor detects a hot water demand the Pump Manager turns on the pump and rushes water out to where it is needed.

    The report Control Rod Drive Hydraulic System Maintenance () identified the best practices and characteristic weaknesses in the control rod drive (CRD) hydraulic system and provided a cost-effective approach to maintaining the system to achieve the highest standard of equipment availability and reliability. The report will be available. In a PWR, the control rods are inserted from the top of the reactor vessel head; in a BWR they are inserted from the bottom. PWRs use CRDM (Control Rod Drive Motor) an electromagnetic drive which inserts and removes the rods in a stepped method, w.

    The report Control Rod Drive Hydraulic System Maintenance will identify the best practices and characteristic weaknesses in the control rod drive (CRD) hydraulic system. It will describe a cost-effective approach to maintaining the system to achieve the highest standard of equipment availability and reliability that will maximize the membership. line rise, a column of liquid refrigerant remains atop the volume of refrigerant gas in the condenser whenever the unit stops. The liquid refrigerant will eventually drain down the line and may fill the condenser perhaps even overflow to the compressor. Sloping the liquid line toward the evaporator creates a gas trap at the line’s highest.


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Interim technical report on BWR feedwater and control rod drive return line nozzle cracking by U.S. Nuclear Regulatory Commission. Division of Operating Reactors Download PDF EPUB FB2

NUREG, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking.a The report provides the staff's resolution of the NRC's Generic echnical Activity A, which is an."Unresolved Safety Issue" pursuant to Section of the Energy Reorganization Act of Get this from a library. Interim technical report on BWR feedwater and control rod drive return line nozzle cracking.

[U.S. Nuclear Regulatory Commission. Division of Operating Reactors.]. Technical Report: BWR feedwater nozzle and control rod drive return line nozzle cracking; resolution of generic technical activity A Technical report.

Get this from a library. BWR feedwater nozzle and control rod drive return line nozzle cracking: resolution of Generic Technical Activity A [R P Snaider; U.S.

Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.;]. BWR feedwater nozzle and control rod drive return line nozzle cracking: resolution of Generic Technical Activity A BWR feedwater nozzle and control rod drive return line nozzle cracking.

Washington, D.C.: U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, (OCoLC) Material Type: Government publication, National government publication: Document Type: Book: All Authors / Contributors: R P Snaider; U.S. Nuclear Regulatory.

@article{osti_, title = {BWR feedwater nozzle and control rod drive return line nozzle cracking; resolution of generic technical activity A Technical report}, author = {Snaider, R}, abstractNote = {This report summarizes work performed by the NRC staff in the resolution of Generic Technical Activity A, 'BWR Nozzle Cracking'.

Generic Technical Activity A is one of the. NUREG, "Interim Technical Report on BWR Feedwater and Control Rod Drive Return Line Nozzle Cracking") and high occupational exposures asso ciated with past repair efforts, the staff is concerned with licensees' efforts to reduce these exposures to ALARA values.

There are several. As required by NUREG, "Interim Technical Report on BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking," an inservice UT and dye penetrant (PT) examination of the four feedwater nozzles was performed by GE during the refueling outage.

No significant changes from the baseline examinations were observed. In addition. A technical report of the experiment can be found in the April issue of the American Sociological Review.

BWR feedwater nozzle and control rod drive return line nozzle cracking. As required by NUREG, "Interim Technical Report on BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking," an inservice UT and dye penetrant (PT) examination of the four feedwater nozzles was performed by GE during the refueling outage.

No significant changes from the baseline examinations were observed. Steam line Reactor vessel Feedwater Core Feed pumps Demineralizer Condensate pumps Turbine generator Separators & BWR Control Rod Drive SystemBWR Control Rod Drive System: Image by MIT OpenCourseWare.

Nozzle – 1 per Jet Pump Riser. the CRD RL as discussed in NUREG, "Interim Technical Report on BWR Feedwater and Control Rod Drive Return Line Cracking," July In your submittal dated Aug you indicated your intent to cut and cap the CRD RL on Unit No. Snaider, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking, NUREG for comment, U.S.

Nuclear Regulatory Commission, Washington, D.C. (April ). Google Scholar 6. This technical report documents a simulator for autonomous vehicles which has been implemented in the MATLAB/SIMULINK environment. BWR feedwater nozzle and control rod drive return line nozzle. – Number of control rods: – Cross shaped absorber blades – Absorber material: B 4C and Hafnium – Absorber length: m – Driven by electrical motor from bottom to top in - out in normal operation (speed 3 cm/s), total insertion time s – Fast shut down hydraulically: Speed cm/s, total insertion time s Technical Data.

The Electric Power Research Institute (EPRI) conducts research, development, and demonstration projects for the benefit of the public in the United States and internationally.

As an independent, nonprofit organization for public interest energy and environmental research, we focus on electricity generation, delivery, and use in collaboration with the electricity sector, its stakeholders and.

The control rod drive (CRD) system is composed of three major elements: the fine motion control rod drive makeup water to the RPV when the feedwater flow is not available.

shaft and a ball check valve at the point of connection with the scram inlet line. These features prevent control rod ejection in the event of a failure of the scram. BWR feedwater nozzle and control rod drive return line nozzle cracking: resolution of Generic Technical Activity A (Washington, D.C.: U.S.

Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, ), by U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation and U.S. Nuclear Regulatory Commission Office of. Get this from a library.

Report on BWR control rod drive mechanical failures: technical activity B [K N Jabbour; U.S. Nuclear Regulatory Commission. Division of Operating Reactors.]. The U.S. is home to more than 30 boiling water reactors of BWR-3 through -6 vintage.

At one time or another, all have experienced obsolescence, reliability, or control [email protected]{osti_, title = {Control rod drive for nuclear reactors. [BWR; PWR]}, author = {Eschenfelder, G and Schultz, R}, abstractNote = {A nuclear reactor control rod drive for finely adjustable normal insertion and withdrawal of control rods from the reactor core, for scramming the control rods, as well as for locking the control rods in their respective rated position, the insertion.Oskarshamn 3 Control rod shafts (27 pcs.) Oskarshamn 3 Core shroud cover Oskarshamn 3 Steam dryer Peach Bottom 2 Steam dryer Mühleberg Fuel channels Peach Bottom 3 Steam dryer Barsebäck 1 & 2 All reactor vessel internals Philippsburg 1 All reactor vessel internals Disc saw (Olkiluoto 1, ) BWR internals.