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Pradip S Saha, 763404 Great Bear Ln, Raleigh, NC 27614

Known as:
Pradip Sikha Saha Sikha Saha Padip Saha
Related to:
Jessica C Jordan 47

Pradip Saha Phones & Addresses

3404 Great Bear Ln, Raleigh, NC 27614    910-6169247   

608 Grange St, Wilmington, NC 28411    910-6864683   

47 Mystic St, Arlington, MA 02474    781-6432214   

White Lake, MI   

Acton, MA   

New York, NY   

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Pradip Saha resumes & CV records

Resumes

Pradip Saha Photo 25

Principal Engineer - Thermal Hydraulic Methods

Location:
Wilmington, NC
Industry:
Mechanical Or Industrial Engineering
Work:
Ge Power
Principal Engineer - Thermal Hydraulic Methods Massachusetts Institute of Technology (Mit) Jan 2003 - Jun 2005
Research Scientist Flotherm Consultants 1986 - 2002
Chairman and Managing Director
Education:
Georgia Institute of Technology 1970 - 1974
Skills:
Finite Element Analysis, Project Engineering, Engineering, Engineering Management, Thermal, Hydraulics
Pradip Saha Photo 26

Pradip Saha

Location:
Wilmington, NC
Industry:
Mechanical Or Industrial Engineering
Work:
Ge Hitachi Nuclear Energy Jul 2005 - May 2017
Retired As Principal Engineer Mit Cambridge Ma Usa Jan 2003 - Jun 2005
Research Scientist and Engineer Flotherm Consultant Feb 1986 - Oct 2002
Chairman and Managing Director
Education:
Univ. of Calcutta (Bengal Engg. College) 1963 - 1968
Bachelor of Engineering, Bachelors, Mechanical Engineering
Skills:
World Class Two Phase Flow Expert, Nuclear Reactor Safety Expert, Ph. D. Thesis Guide, Started His Own Company, Led Highly Qualified Engineers In Energy Field, Expert In Role of Nuclear Energy, Nuclear Reactor Thermal Hydraulics, Power Generation, Heat Transfer, Project Management, Energy, Reactor, Renewable Energy, Engineering Management, Power Plants, Nuclear Engineering, Simulations, Nuclear, Finite Element Analysis, Fortran, Process Engineering
Interests:
Economic Empowerment
Education
Environment
Science and Technology
Health
Pradip Saha Photo 27

Pradip Saha

Pradip Saha Photo 28

Pradip Kumar Saha

Pradip Saha Photo 29

Pradip Saha

Pradip Saha Photo 30

Pradip Saha

Location:
United States

Publications & IP owners

Us Patents

Feedwater Temperature Control Methods And Systems

US Patent:
2009001, Jan 15, 2009
Filed:
Jul 13, 2007
Appl. No.:
11/777377
Inventors:
Stephan Craig Moen - Wilmington NC, US
Jack Patrick Noonan - Wilmington NC, US
Pradip Saha - Wilmington NC, US
International Classification:
G21C 7/00
US Classification:
376210
Abstract:
In various embodiments, a system for controlling the power level of a natural circulation boiling water nuclear reactor (NCBWR) is provided. In various embodiments, the system includes a heating subsystem for heating feedwater flowing into an annulus of a NCBWR to increase the temperature of recirculation water flowing through the core above a predetermined recirculation water operating temperature. Additionally the system includes a temperature sensor operable to sense the temperature of the feedwater flowing into the annulus. The temperature sensor is communicatively connected to a temperature controller operable to command the heating subsystem to increase the temperature of the feedwater flowing into the annulus to a requested temperature above a predetermined operating temperature of the feedwater flowing into the annulus. By increasing the temperature of the feedwater flowing into the annulus, the temperature of the recirculation water is increased above the predetermined recirculation water operating temperature causing a reduction in the power level generated by the NCBWR core.

Salt Filtration System And Method Of Removing A Radioactive Material From A Gas Using The Same

US Patent:
2015031, Nov 5, 2015
Filed:
May 5, 2014
Appl. No.:
14/269505
Inventors:
Eric Paul LOEWEN - Wilmington NC, US
Pradip SAHA - Wilmington NC, US
Emma LEBWOHL - Wilmington NC, US
Kelly Ann FITZWATER - Wilmington NC, US
Assignee:
GE-Hitachi Nuclear Energy Americas LLC - Wilmington NC
International Classification:
B01D 59/50
B01D 53/22
B01D 53/14
Abstract:
A method of removing a radioactive material from a gas includes directing the gas through a bed of salt, wherein the gas includes water vapor and the radioactive material. The salt constitutes more than 50 percent by weight of the bed. The method additionally includes condensing the water vapor in the bed and dissolving a portion of the salt to form a salt solution. The method further includes absorbing the radioactive material into the salt solution while a remainder of the gas passes through the bed. A salt filtration system configured to perform the method may be implemented as a pre-filter (or post-filter) to an existing filter unit or as a standalone filter.

Passive Shutdown System And Method Of Operating A Liquid Metal Cooled Reactor Using The Same

US Patent:
2015020, Jul 16, 2015
Filed:
Jan 14, 2014
Appl. No.:
14/154593
Inventors:
Eric Paul LOEWEN - Wilmington NC, US
Weston Matthew CUNDIFF - Wilmington NC, US
Pradip SAHA - Wilmington NC, US
Derek BASS - Wilmington NC, US
Assignee:
GE-HITACHI NUCLEAR ENERGY AMERICAS LLC - Wilmington NC
International Classification:
G21C 7/22
G21C 7/32
Abstract:
A passive shutdown system for a liquid metal cooled reactor may include a tube and a neutron absorber within the tube. The tube may be configured to extend through a core of the liquid metal cooled reactor. The tube has an upper end and a lower end. The tube defines a flow path for a liquid metal coolant. The neutron absorber is a mobile structure configured to partially obstruct a flow of the liquid metal coolant within the flow path. A method of operating a liquid metal cooled reactor may involve the use of the passive shutdown system.

Feedwater Temperature Control Methods And Systems

US Patent:
2014022, Aug 14, 2014
Filed:
Apr 21, 2014
Appl. No.:
14/257608
Inventors:
- Wilmington NC, US
Jack Patrick NOONAN - Wilmington NC, US
Pradip SAHA - Wilmington NC, US
Assignee:
GE-HITACHI NUCLEAR ENERGY AMERICAS LLC - Wilmington NC
International Classification:
G21C 7/32
US Classification:
376210, 376241
Abstract:
A system for controlling the power level of a natural circulation boiling water nuclear reactor (NCBWR) may include a heating subsystem for heating feedwater flowing into an annulus of the NCBWR to increase the temperature of recirculation water flowing through the core above a predetermined recirculation water operating temperature. Additionally the system may include a temperature sensor operable to sense the temperature of the feedwater flowing into the annulus. The temperature sensor is communicatively connected to a temperature controller operable to command the heating subsystem to increase the temperature of the feedwater flowing into the annulus to a requested temperature above a predetermined operating temperature of the feedwater flowing into the annulus. By increasing the temperature of the feedwater flowing into the annulus, the temperature of the recirculation water is increased above the predetermined recirculation water operating temperature causing a reduction in the power level generated by the NCBWR core.

Possible Relatives

Debashis Saha  Debjani Saha  Deepankar Saha  Gautam Saha  Gopal H Saha  Henry S Saha  Jayanta K Saha  Pradip D Patel  Pradip K Pramanik  Pradip K Das 

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