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Scott J Shargots

from Forest, VA
Age ~39
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Related to:
James E Burchfield, 97Megan J Larue, 33Chelsea J Larue, 33Mabel E Shargots, 66Dean Jungo, 66Eric R Shargots, 36James R Shargots, 66Kristin L Jungo, 39Susan L Jungo, 65Nicole L Jungo, 37
Connected to:
Abdo S Sharhan, 49Mike M Shari, 58Abbas Shariat, 80Afsaneh Shariati, 59Amir Shariati, 52Farshid Shariatzadeh, 42Goli Shariat, 50Jeff Shariat, 43Jonathan N Shariat, 37Noushin Shariati, 60

Scott Shargots Phones & Addresses

  • 107 Tyler Ter, Forest, VA 24551 (724) 255-1386
  • Lynchburg, VA
  • Cuyahoga Falls, OH
  • Washington, PA
  • Akron, OH

Work

Company: Babcock & wilcox Jan 2010 to Jan 2010 Position: Engineer

Education

Degree: Bachelors, Bachelor of Science School / High School: The University of Akron 2003 to 2008 Specialities: Civil Engineering

Skills

Asme Y14.5 • Asme B31.1 • Asme B31.3 • Aisc • Aci Codes • Nds • Asce 7 • Nureg 0800 • Nrc 10 Cfr 50 • Nqa 1 • Autocad • Solidworks • Staad Pro • Caesar Ii • Microsoft Office

Industries

Mechanical Or Industrial Engineering

Resumes

Resumes

Scott Shargots Photo 1

Scott Shargots

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Location:
107 Tyler Ter, Forest, VA 24551
Industry:
Mechanical Or Industrial Engineering
Work:
Babcock & Wilcox Jan 2010 - Jan 2010
Engineer
The Home Depot Jul 2005 - Oct 2008
Sales Associate
Crown Castle Dec 2007 - Jan 2008
Engineering Intern
Education:
The University of Akron 2003 - 2008
Bachelors, Bachelor of Science, Civil Engineering
Skills:
Asme Y14.5
Asme B31.1
Asme B31.3
Aisc
Aci Codes
Nds
Asce 7
Nureg 0800
Nrc 10 Cfr 50
Nqa 1
Autocad
Solidworks
Staad Pro
Caesar Ii
Microsoft Office

Publications

Us Patents

Reactor Vessel

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US Patent:
D691085, Oct 8, 2013
Filed:
Sep 21, 2011
Appl. No.:
29/402102
Inventors:
Scott J. Shargots - Forest VA, US
Matthew W. Ales - Forest VA, US
Assignee:
Babcock & Wilcox Nuclear Energy, Inc. - Charlotte NC
International Classification:
1302
US Classification:
D13101

Terminal Elements For Coupling Connecting Rods And Control Rods In Control Rod Assemblies For A Nuclear Reactor

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US Patent:
20120051482, Mar 1, 2012
Filed:
Aug 24, 2010
Appl. No.:
12/862124
Inventors:
Scott J. Shargots - Lynchburg VA, US
Mathew W. Ales - Forest VA, US
International Classification:
G21C 7/06
US Classification:
376219
Abstract:
A nuclear reactor includes a pressure vessel, and a control rod assembly (CRA) including at least one movable control rod, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a connecting rod engaged with the CRDM and a terminal element connected with a lower end of the connecting rod and further connected with the at least one control rod. In some embodiments the terminal element includes a first portion comprising a first material having a first density and a second portion comprising a second material having a second density that is greater than the first density. In some embodiments the terminal element has a largest dimension parallel with the connecting rod that is greater than or equal to a largest dimension transverse to the connecting rod.

Support Structure For A Control Rod Assembly Of A Nuclear Reactor

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US Patent:
20120099691, Apr 26, 2012
Filed:
Oct 21, 2010
Appl. No.:
12/909252
Inventors:
Scott J. Shargots - Lynchburg VA, US
Mathew W. Ales - Forest VA, US
International Classification:
G21C 7/08
G21C 7/117
US Classification:
376219, 376353
Abstract:
A control rod guide frame comprises a self supporting stack of two or more columnar elements defining a central passage. The columnar elements may include mating features that mate at abutments between adjacent columnar elements of the stack. The control rod guide frame is suitably used in conjunction with a control rod drive mechanism (CRDM) operatively connected with at least one control rod, and a nuclear reactor core, in which the CRDM moves the at least one control rod into and out of the nuclear reactor core under guidance of the control rod guide frame. In another embodiment, a control rod guide frame comprises a stack of two or more columnar elements defining a central passage having a constant cross-section as a function of position along the central passage. In another embodiment, a control rod guide frame comprises an extruded columnar element providing continuous control rod guidance.

Pressurized Water Reactor With Upper Vessel Section Providing Both Pressure And Flow Control

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US Patent:
20120294405, Nov 22, 2012
Filed:
May 17, 2011
Appl. No.:
13/109120
Inventors:
Scott J. Shargots - Lynchburg VA, US
International Classification:
G21C 15/24
B23P 17/00
G21C 19/20
US Classification:
376260, 376361, 29888
Abstract:
A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an internal pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the internal pressurizer. A central riser may be disposed concentrically inside the pressure vessel, and the RCP impels primary coolant downward into a downcomer annulus between the central ser and the pressure vessel. A steam generator may be disposed in the downcomer annulus and spaced apart from with the impeller by an outlet plenum, A manway may access the outlet plenum so tube plugging can be performed on the steam generator via access through the manway without removing the RCP.

Pressurized Water Reactor With Reactor Coolant Pumps Operating In The Downcomer Annulus

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US Patent:
20130028367, Jan 31, 2013
Filed:
Jul 28, 2011
Appl. No.:
13/192735
Inventors:
Scott J. Shargots - Forest VA, US
Mathew W. Ales - Forest VA, US
Michael J. Edwards - Forest VA, US
Randall J. Paliga - Lynchburg VA, US
International Classification:
G21C 15/25
US Classification:
376372
Abstract:
A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel and a nuclear reactor core disposed in a lower vessel section. A hollow cylindrical central riser is disposed concentrically inside the pressure vessel. A downcomer annulus is defined between the central riser and the pressure vessel. A reactor coolant pump (RCP) includes (i) an impeller disposed above the nuclear reactor core and in fluid communication with the downcomer annulus to impel primary coolant downward through the downcomer annulus, (ii) a pump motor disposed outside of the pressure vessel, and (iii) a drive shaft operatively connecting the pump motor with the impeller. The PWR may include an internal steam generator in the downcomer annulus, with the impeller is disposed below the steam generator. The impeller may be disposed in the downcomer annulus. The RCP may further comprise a pump casing that with the impeller defines a centrifugal pump.

Pressurized Water Reactor With Upper Vessel Section Providing Both Pressure And Flow Control

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US Patent:
20130108005, May 2, 2013
Filed:
Oct 26, 2011
Appl. No.:
13/282217
Inventors:
Scott J. Shargots - Forest VA, US
International Classification:
G21C 15/00
G21C 21/00
US Classification:
376361, 2988802
Abstract:
A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.

Pressurized Water Reactor With Upper Plenum Including Cross-Flow Blocking Weir

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US Patent:
20130121453, May 16, 2013
Filed:
Nov 10, 2011
Appl. No.:
13/293899
Inventors:
Scott J. Shargots - Forest VA, US
Matthew W. Ales - Forest VA, US
Michael J. Edwards - Forest VA, US
Andrew C. Whitten - Lynchburg VA, US
International Classification:
G21C 15/00
G21C 15/18
US Classification:
376282, 376361, 376399, 376395
Abstract:
A pressurized water reactor (PWR) comprises: a nuclear core comprising a fissile material; a cylindrical pressure vessel having a vertically oriented cylinder axis and containing the nuclear core immersed in primary coolant water; and a hollow cylindrical central riser disposed concentrically with and inside the cylindrical pressure vessel. A downcomer annulus is defined between the hollow cylindrical central riser and the cylindrical pressure vessel. The hollow cylindrical central riser has a radially expanding upper orifice that merges into an annular divider plate that separates an upper plenum above the annular divider plate from a lower plenum below the annular divider plate. The upper plenum is in fluid communication with the radially expanding upper orifice and the lower plenum is in fluid communication with the downcomer annulus. A weir may extend away from a bottom wall of the lower plenum into the lower plenum. An emergency core cooling system (ECCS) return line nozzle may be arranged to inject water into the upper plenum. A pump support plate spans the inner diameter of the cylindrical pressure vessel and forms a portion of the pressure boundary of the cylindrical pressure vessel, and reactor coolant pumps (RCPs) are supported by the pump support plate. Alternatively, reactor coolant pumps (RCPs) are supported by an arcuate annular ledge formed in the upper portion of the cylindrical pressure vessel.

Control Rod Drive Mechanism (Crdm) Mounting System For Pressurized Water Reactors

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US Patent:
20130223580, Aug 29, 2013
Filed:
Feb 27, 2012
Appl. No.:
13/405405
Inventors:
Scott J Shargots - Forest VA, US
International Classification:
G21C 7/16
G21C 7/14
H05K 13/00
G21C 7/12
US Classification:
376229, 376228, 376219, 376230, 29854
Abstract:
A standoff supporting a control rod drive mechanism (CRDM) in a nuclear reactor is connected to a distribution plate which provides electrical power and hydraulics. The standoff has connectors that require no action to effectuate the electrical connection to the distribution plate other than placement of the standoff onto the distribution plate. This facilitates replacement of the CRDM. In addition to the connectors, the standoff has alignment features to ensure the CRDM is connected in the correct orientation. After placement, the standoff may be secured to the distribution plate by bolts or other fasteners. The distribution plate may be a single plate that contains the electrical and hydraulic lines and also is strong enough to provide support to the CRDMs or may comprise a stack of two or more plates.
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Scott J Shargots from Forest, VA, age ~39 Get Report