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Fusion Research Center Annual Report Series

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Georgia Tech Fusion Research Center Annual Report 2011

2011-09 , Stacey, Weston M. , Stacey, Weston M.

The Georgia Tech wor kon interpretation of the DIII-D experiment and on the development of the fission-fusion hybrid burner reactor (SABR) concept is described.

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SABR Dynamical Safety Analysis

2008 , Stacey, Weston M. , Sumner, Tyler Scott , Van Rooijen, W.

A model was developed to simulate the coupled dynamics of a sub-critical fast reactor fueled with transuranics (TRU), a DT tokamak fusion neutron source and the heat removal and secondary systems. Several types of accident initiating events—inadvertent increases in the auxilliary power and fueling sources for the fusion neutron source, inadvertent control rod ejection from the reactor core, loss of flow (LOFA), and loss of heat sink (LOHSA)—were simulated in order to determine the time available to detect accident onset and take corrective action. A more detailed description is presented in Ref. 1.

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Calculation of SOL and Divertor Plasma Properties

2008 , Stacey, Weston M.

A complex variety of interacting phenomena determine the properties of the plasma in the scrape-off layer (SOL) and divertor of a tokamak. These phenomena have been modeled in, two-dimensional plasma edge codes, which provide important insights into the physics of the SOL and divertor regions, but which are computationally intensive. In order to provide the means for routine analyses of SOL and divertor plasma properties, a computationally tractable model for the calculation of ion and impurity densities, temperature, currents, particle flows and electric fields along the separatrix in the divertor and scrape-off layer of tokamak plasmas has been developed. This model is described and applied to calculate the effects of particle drifts and the direction of the toroidal magnetic field on these calculated quantities. Several recently observed experimental phenomena—double reversal of the parallel ion velocity in the SOL, enhanced core penetration of argon injected into the divertor when the grad-B ion drift is into rather than away from the divertor—and other interesting phenomena, such as the structure of the parallel current flowing in the SOL and the reversal of the sign of the electrostatic potential in the SOL when the toroidal field direction is reversed, are predicted.

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HEP Benchmarking Activity

2008 , Stacey, Weston M.

A group of people are collaborating in the comparison experimental thermal diffusivities inferred from experimental data measured in the edge pedestal of DIII-D H-mode discharges using different codes. I am providing calculations based on a 1D edge transport code (as described in section II and Ref. 1), Rich Groebner (General Atomics) is providing calculations based on the 1.5D transport/MHD code ONE-TWO2, Tarig Rafiq (Lehigh) is providing calculations based on the Multimode transport model in the 1.5D transport/MHD code ASTRA3, Tom Rognlien (Lawrence Livermore National Laboratory) is providing calculations based on the 2D transport code UEDGE4, and Larry Owen and John Canick (Oak Ridge National Laboratory) are providing calculations based on the 2D transport code SOLPS5. Jim Callen (Wisconsin) is coordinating the activity.

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Annual Report 2010: Fusion Research Center, Nuclear and Radiological Engineering Program, Georgia Institute Of Technology

2010-09 , Stacey, Weston M.

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Comparison of the Theoretical and Experimental Heat Diffusivities in the DIII-D Edge plasma

2008 , Stacey, Weston M.

Predictions of theoretical models for ion and electron heat diffusivity have been compared against experimentally inferred values of the heat diffusivity profile in the edge plasma of two H-mode and one L-mode discharge in DIII-D [J. Luxon, Nucl. Fusion, 42, 614 (2002)]. Various widely used theoretical models based on neoclassical, ion temperature gradient modes, drift Alfven modes and radiative thermal instability modes for ion transport, and based on paleoclassical, electron temperature gradient modes, trapped electron modes, and drift resistive ballooning modes for electron transport were investigated.

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Edge Pedestal Structure and Transport Interpretation in DIII-D (In the absence of or in between ELMs)

2008 , Stacey, Weston M. , Groebner, Rich J.

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2009 Annual Report

2009-01-01 , Stacey, Weston M.

Research Summary: During 2009, research focused on i) interpretation of plasma edge experiments in DIII-D (DoE Grant DE-FG02-99-ER54538), ii) further analysis of the SABR fusionfission hybrid actinide burner reactor concept developed at Georgia Tech (DoE Grant DE-SC0002202), and iii) related topics in theoretical/computation plasma physics. This work and publication/presentations based on it are summarized in this report.

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SABR Fuel Cycle Analysis

2008 , Stacey, Weston M. , Sommer, Christopher , Van Rooijen, W.

Various fuel cycles for a sodium cooled, subcritical, fast reactor, SABR, with a fusion neutron source for the transmutation of light water reactor spent fuel have been analyzed. All fuel cycles were 4-batch, and all but one were constrained by a total fuel residence time consistent with a 200 dpa clad and structure materials damage limit. The objective of this study was to achieve greater than 90% burn up of the transuranics from the spent fuel, consistent with the Advanced Fuel Cycle objectives of DoE. A more detailed account of this work can be found in the MS thesis of the first author.

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Implementation of the GTNEUT 2D Neutrals Transport Code for Routine DIII-D Analyses

2008 , Stacey, Weston M. , Rognlien, Thomas D. , Groebner, Rich J. , Friis, Zachary Ward

The Georgia Tech Neutral Transport (GTNEUT) code is being implemented to provide a tool for routine analysis of the effects of neutral atoms on edge phenomena in DIII-D. GTNEUT can use an arbitrarily complex two-dimensional grid to represent the plasma edge geometry. The grid generation capability built into the UEDGE code, which utilizes equilibrium fitting data taken from experiment, is being adapted to produce geometric grids for the complex 2D geometries in the DIII-D plasma edge. The process for using experimental measurements supplemented by plasma edge calculations to provide the required background plasma parameters for the GTNEUT calculation will be systematized once the geometric grid generation is complete.

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