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2012 Summer Student Workshop at Oak Ridge National Laboratory: (left to right) Aaron Thomas (NSCU), James Elliott (NCSU), Doug Kothe (ORNL), Julie Stout (Messiah College), Yuxuan Liu (UM), and Ryan Hon (GIT).

Winner of the 2012 Student Workshop Poster Session: (left to right) Doug Kothe (ORNL), Mitchell Young (UMI), and John Gilligan (NCSU).

Drekar CFD simulation of turbulent flow between fuel rods (3x3 configuration) in a light water reactor. Image on left shows constant velocity magnitude, surface colored by vorticity.

Demonstration of fully coupled implicit Drekar simulation of conjugate heat transfer in 3x3 configuration.

Drekar simulation of conjugate heat transfer and fluid flow in a reactor core with heat transfer in pin, cladding and fluid. A UQ analysis yields the temperature profile uncertainty at 3 heights in the reactor resulting from uncertainty in the fuel source term and inflow velocity.

Cladding wear due to grid-to-rod-fretting (GTRF) can lead to fuel rod leaks in pressurized water reactors. The manifestation of this failure mechanism is complex, involving many factors ranging from basic material properties to operating conditions.

Cladding wear due to grid-to-rod-fretting (GTRF) can lead to fuel rod leaks in pressurized water reactors. The manifestation of this failure mechanism is complex, involving many factors ranging from basic material properties to operating conditions.

Peregrine 3D model of a LWR fuel rodlet with the center pellet containing a Missing Pellet Surface (MPS).

Peregrine results from the 3D MPS simulation showing the temperature in the fuel (left) and the effective (Mises) stress in the clad (right).

Secretary of Energy Steven Chu takes a 3D tour of a virtual reactor in CASL’s Immersive Visualization and Analysis Center.

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Simulation of 3D fission power distribution of a PWR core. Transport calculations that are pin detailed provide accurate prediction of pin power distribution. This analysis capability is above and beyond what existing modeling and simulation tools can do.

Science and Technology

Probing the mysteries of cracks and stresses

Diving into a pool from a few feet up allows you to enter the water smoothly and painlessly, but jumping from a bridge can lead to a fatal impact.

Posted on September 28, 2012
Public Release of CASL Infrastructure Software

The Virtual Environment for Reactor Applications (VERA) comprises a suite of tools for scalable simulation of nuclear reactor core behavior.

Posted on September 24, 2012
Nuclear Energy - Supercomputer speeds path forward

When run on graphics processing units, Denovo ran 3.5 times faster than what was possible with ORNL's Jaguar, which uses only central processing units.

Posted on August 31, 2012
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Partners

CASL connects fundamental research and technology development through an integrated partnership of government, academia, and industry that extends across the nuclear energy enterprise.

Probing the mysteries of cracks and stresses

Public Release of CASL Infrastructure Software

Nuclear Energy - Supercomputer speeds path forward