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Filtering by: Subject Water cooled reactors -- Oregon -- Corvallis Remove constraint Subject: Water cooled reactors -- Oregon -- Corvallis Degree Field Nuclear Engineering Remove constraint Degree Field: Nuclear Engineering

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MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

Creator:

Merritt, Patrick A.

Resource Type:

Masters Thesis

Full Text:

) Physical Description The Oregon State University TRIGAlo Mark II Reactor (OSTR) is a light-water cooled
Scaling study of the depressurized conduction cooldown event in the high temperature test facility using RELAP5-3D/ATHENA

Creator:

Aldridge, Robert J.

Abstract:

In 2008, the Department of Energy (DOE) and Nuclear Regulatory Commission (NCR) decided that the Next Generation Nuclear Plant (NGNP) would be the Very High Temperature Reactor (VHTR). In support of the licensing and validation effort of the VHTR, Oregon State University was tasked with designing, building, and operating a...

Resource Type:

Masters Thesis

Full Text:

Simplified Boiling Water Reactor GCFR Gas Cooled Fast Reactor GR-SAC Gas Reactor Severe Accident Code
Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility

Creator:

Utberg, John E., Jr

Abstract:

The Modular High Temperature Gas-Cooled Reactor (MHTGR) is a graphite moderated reactor that utilizes helium as its coolant. One consideration of importance is how the MHTGR will perform during a Depressurized Conduction Cooldown (DCC) accident, which generally can be divided into three phases: depressurization, air ingress, and natural circulation. After...

Resource Type:

Masters Thesis

Full Text:

Temperature Gas-Cooled Reactor NGNP Next Generation Nuclear Plant OSU Oregon State University PCC
Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

Creator:

Castañeda, Juan A.

Abstract:

In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear...

Resource Type:

Masters Thesis

Full Text:

), Supercritical-Water-Cooled Reactor (SCWR) and the Very-High-Temperature Reactor (VHTR). [2] In the United

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Academic Affiliation

Nuclear Engineering and Radiation Health Physics3
Nuclear Engineering1

Advisor

Woods, Brian G.3
Klein, Andrew C.1

Commencement Year

Commencement Year range begin – Commencement Year range end

Current results range from 2000 to 2014

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Committee Member

Klein, Andrew1
Krane, Kenneth1
Marcum, Wade1
Marcum, Wade R.1
Palmer, Todd S.1
more Committee Members »

Creator

Aldridge, Robert J.1
Castaneda, Juan A.1
Merritt, Patrick A.1
Utberg, John E., jr1

Date

Date range begin – Date range end

Current results range from 1999 to 2014

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Decade

2010-20193
1990-19991

Degree Field

Nuclear Engineering[remove]4

Degree Level

Master's4

Degree Name

Master of Science (M.S.)4

Language

English [eng]4

License

All rights reserved3

Non-Academic Affiliation

Oregon State University. Graduate School4

Peer Reviewed

No4

Resource Type

Masters Thesis4

Rights Statement

In Copyright3
Copyright Not Evaluated1

Subject

Gas cooled reactors -- Cooling -- Oregon -- Corvallis2
Gas cooled reactors -- Oregon -- Corvallis -- Fluid dynamics1
Gas cooled reactors -- Oregon -- Corvallis -- Safety measures -- Testing1
Gas cooled reactors -- Oregon -- Corvallis -- Testing1
Gas cooled reactors -- Safety appliances -- Testing -- Oregon -- Corvallis1
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