University of Wisconsin Neutronics Center of Excellence

ST-FNSF

isometric of ST-FNSF device

ST-FNSF

Neutronics Model of ST-FNSF

3-D Neutronics Model for Shielding and TBR Analyses

Tritium production in ST-FSNF

3-D Tritium production distribution in outboard blanket of ST-FNSF

International fusion roadmaps, from ITER to the first power plant, take different approaches and levels of risk, depending on the degree of extrapolation beyond ITER and the wide range of near-term and advanced power plants. In the US, the Fusion Nuclear Science Facility (FNSF) is viewed as an essential element of the fusion roadmap. It provides a validated technical basis for a fusion demonstration (DEMO) plant and could be constructed in parallel or follow the ITER experiment. More specifically, a FNSF provides the high neutron flux and fluence environment needed to develop fusion materials and components.

The spherical tokamak (ST) is a leading candidate for a FNSF due to its compact size and modular configuration. Previous "pilot plant" studies by the Princeton Plasma Physics Laboratory identified key research needs and design issues for ST-based FNSF devices and motivated studies of the impact of device size on neutron wall loading, tritium breeding, and electricity production. Understanding the impact of varied device size is an important ongoing ST research activity at PPPL. A near-term neutronics issue that is being addressed is the impact of device size on tritium breeding ratio where smaller devices (with R < 1.6 m) will likely have more difficulty achieving TBR > 1 since a higher fraction of in-vessel surface area must be dedicated to auxiliary heating ports and blanket test modules.


Publications

Results: 1 to 13 of 13 order by: UWFDM Author Title Date

UWFDM-1424   Shielding and Activation Analyses for Outboard Region of FESS-FNSF Design; M.T. Elias, and L. El-Guebaly, November 2015. (34 pages, 2.7 MB)

UWFDM-1423   Shielding and Activation Analyses for Inboard Region of FESS-FNSF Design; B.M. Madani, and L. El-Guebaly, November 2015. (43 pages, 2.6 MB)

UWFDM-1421   Preliminary 3-D Modeling and Neutronics Analysis for FESS-FNSF Design; Moataz S. Harb, and L. El-Guebaly, September 2015. (12 pages, 1.3 MB)

Nuclear Aspects and Blanket Testing/Development Strategy for ST-FNSF; L. El-Guebaly, L. Mynsberge, J. Menard, T. Brown, S. Malang, L. Waganer, May 2014 [IEEE Journal: Transactions on Plasma Science, 42, No. 5, 1457-1463 (May 2014).].

Progress in Developing the STFNSF Configuration; T. Brown, J. Menard, P. Titus, A. Zolfaghari, L. El-Guebaly, and L. Mynsberge, September 2013 [CD-ROM of 2013 IEEE 25th Symposium on Fusion Engineering (SOFE), San Francisco, June 10-14, 2013. ISBN: 978-1-4799-0169-2, IEEE Cat. Number: CFP13SOF-CDR (September 2013)].

TBR and Shielding Analysis in Support of ST-FNSF Study; L. El-Guebaly, L. Mynsberge, A. Jaber, J. Menard, and T. Brown, September 2013 [CD-ROM of 2013 IEEE 25th Symposium on Fusion Engineering (SOFE), San Francisco, June 10-14, 2013. ISBN: 978-1-4799-0169-2, IEEE Cat. Number: CFP13SOF-CDR (September 2013)].

ST-FNSF Mission and Performance Dependence on Device Size; J. Menard, T. Brown, J. Canik, L. El-Guebaly, S. Gerhardt, A. Jaber, S. Kaye, E. Meier, L. Mynsberge, C. Neumeyer, M. Ono, R. Raman, S. Sabbagh, V. Soukhanovskii, P. Titus, G. Voss, R. Woolley, A. Zolfaghari, June 10-14, 2013 [presented at 25th Symposium on Fusion Engineering (SOFE), San Francisco, CA, June 10-14, 2013].

retrieve PDF TBR and Shielding Analyses in Support of ST-FNSF Study; L. El-Guebaly, L. Mynsberge, A. Jaber, J. Menard, T. Brown, June 2013 [presented at the 25th Symposium on Fusion Engineering (SOFE), 10-14 June 2013, San Francisco, CA]. (1 page, 2.6 MB)

Comparison of Options for a Pilot Plant Fusion Nuclear Mission; T. Brown, A. E. Costley, R.J. Goldston, L. El-Guebaly, C. Kessel, G.H. Neilson, S. Malang, J.E. Menard, S. Prager, L. Waganer, P. Titus, M. Zarnstorff, 2013 [Fusion Science and Technology 61 (2013) 662-669].

Prospects for Pilot Plants Based on the Tokamak, Spherical Tokamak, and Stellarator; J.E. Menard, L. Bromberg, T. Brown, T. Burgess, D. Dix, L. El-Guebaly, T. Gerrity et al., 2011 [Presented at 23rd IAEA Fusion Energy Conference, Daejeon, Korea, October 11-16, 2010. Nuclear Fusion 51 (2011 103014, 13 pp).]. ( available online )

UWFDM-1405   In-Vessel Components and Blanket Development Strategy for PPPL Pilot Plant; L.A. El-Guebaly, S. Malang, L.M. Waganer, September 2011. (15 pages, 618 kB)

An Overview of Pilot Plant Designs Based on the Advanced Tokamak, Spherical Tokamak and Stellarator; T. Brown, L. Bromberg, A.E. Costley, R.J. Goldston, L. El-Guebaly, C. Kessel, G.H. Neilson, S. Malang, J.E. Menard, S. Prager, S. Scott, L. Waganer, M. Zarnstorff, 2011 [Proceedings of 24th Symposium on Fusion Engineering - SOFE-2011, June 26-30, 2011, Chicago, IL, USA. ISBN: 978-1-4673-0103-9. IEEE Catalog Number: CFP11SPF-CDR (2011).].

retrieve PDF Updated Tritium Breeding Requirement in Fusion Nuclear Science Facility (FNSF); Mohamed Sawan, Mohamed Abdou, August 2009 [presented at the Fusion Nuclear Science and Technology (FNST) meeting, 18-20 August 2009, UCLA, Los Angeles CA]. (14 pages, 770 kB)

Results: 1 to 13 of 13 order by: UWFDM Author Title Date