TY - GEN
T1 - Simulation enabled safeguards assessment methodology
AU - Bean, Robert
AU - Bjornard, Trond
AU - Larson, Tom
PY - 2007
Y1 - 2007
N2 - It is expected that nuclear energy will be a significant component of future supplies. New facilities, operating under a strengthened international nonproliferation regime will be needed. There is good reason to believe virtual engineering applied to the facility design, as well as to the safeguards system design will reduce total project cost and improve efficiency in the design cycle. Simulation Enabled Safeguards Assessment MEthodology has been developed as a software package to provide this capability for nuclear reprocessing facilities. The software architecture is specifically designed for distributed computing, collaborative design efforts, and modular construction to allow step improvements in functionality. Drag and drop wireframe construction allows the user to select the desired components from a component warehouse, render the system for 3D visualization, and, linked to a set of physics libraries and/or computational codes, conduct process evaluations of the system they have designed.
AB - It is expected that nuclear energy will be a significant component of future supplies. New facilities, operating under a strengthened international nonproliferation regime will be needed. There is good reason to believe virtual engineering applied to the facility design, as well as to the safeguards system design will reduce total project cost and improve efficiency in the design cycle. Simulation Enabled Safeguards Assessment MEthodology has been developed as a software package to provide this capability for nuclear reprocessing facilities. The software architecture is specifically designed for distributed computing, collaborative design efforts, and modular construction to allow step improvements in functionality. Drag and drop wireframe construction allows the user to select the desired components from a component warehouse, render the system for 3D visualization, and, linked to a set of physics libraries and/or computational codes, conduct process evaluations of the system they have designed.
UR - http://www.scopus.com/inward/record.url?scp=45149090007&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:45149090007
SN - 0894480553
SN - 9780894480553
T3 - GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
SP - 1773
EP - 1777
BT - GLOBAL 2007
T2 - GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
Y2 - 9 September 2007 through 13 September 2007
ER -