National Technical Reports Library

The National Technical Information Service acquires, indexes, abstracts, and archives the largest collection of U.S. government-sponsored technical reports in existence. The NTRL offers online, free and open access to these authenticated government technical reports. Technical reports and documents in its repository may be available online for free either from the issuing federal agency, the U.S. Government Publishing Office’s Federal Digital System website, or through search engines.

Details

Visualizing MCNP Tally Segment Geometry and Coupling Results with ABAQUS. 2007 ANS Winter Meeting.

DE2008912910

Publication Date	2007
Personal Author	Parry, J. R.; Galbraith, J. A.
Page Count	3
Abstract	The Advanced Graphite Creep test, AGC-1, is planned for irradiation in the Advanced Test Reactor (ATR) in support of the Next Generation Nuclear Plant program. The experiment requires very detailed neutronics and thermal hydraulics analyses to show compliance with programmatic and ATR safety requirements. The MCNP model used for the neutronics analysis required hundreds of tally regions to provide the desired detail. A method for visualizing the hundreds of tally region geometries and the tally region results in 3 dimensions has been created to support the AGC-1 irradiation. Additionally, a method was created which would allow ABAQUS to access the results directly for the thermal analysis of the AGC-1 experiment.
Keywords	Graphite Irradiation Compliance Creep Dimensions Geometry Monte Carlo method Neutronics Photons Safety Test reactors Thermal analysis Hydraulics Meetings
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Laboratory, Idaho Falls, ID.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200819

Visualizing MCNP Tally Segment Geometry and Coupling Results with ABAQUS. 2007 ANS Winter Meeting.

Visualizing MCNP Tally Segment Geometry and Coupling Results with ABAQUS. 2007 ANS Winter Meeting.
DE2008912910

Publication Date	2007
Personal Author	Parry, J. R.; Galbraith, J. A.
Page Count	3
Abstract	The Advanced Graphite Creep test, AGC-1, is planned for irradiation in the Advanced Test Reactor (ATR) in support of the Next Generation Nuclear Plant program. The experiment requires very detailed neutronics and thermal hydraulics analyses to show compliance with programmatic and ATR safety requirements. The MCNP model used for the neutronics analysis required hundreds of tally regions to provide the desired detail. A method for visualizing the hundreds of tally region geometries and the tally region results in 3 dimensions has been created to support the AGC-1 irradiation. Additionally, a method was created which would allow ABAQUS to access the results directly for the thermal analysis of the AGC-1 experiment.
Keywords	Graphite Irradiation Compliance Creep Dimensions Geometry Monte Carlo method Neutronics Photons Safety Test reactors Thermal analysis Hydraulics Meetings
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Laboratory, Idaho Falls, ID.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200819