University of Wisconsin Neutronics Center of Excellence

ITER

ITER isometric

ITER isometric

40-degree global ITER CAD model used in DAG-MCNP 3-D neutronics

40-degree global ITER CAD model used in DAG-MCNP 3-D neutronics

3-D distribution of nuclear heating in Blanket Module 13

3-D distribution of nuclear heating in Blanket Module 13

Coupling nuclear heating and CFD yields temperatures at steel surface of FW finger (top) and cross section through water pipes (bottom) of Blanket Module 04

Coupling nuclear heating and CFD yields temperatures at steel surface of FW finger (top) and cross section through water pipes (bottom) of Blanket Module 04

Detailed model of Blanket Module 01

Detailed model of Blanket Module 01

Nuclear heating at a slice through Blanket Module 01

Nuclear heating at a slice through Blanket Module 01

Nuclear heating on VV shell showing poloidal manifold water from Blanket Module 01

Nuclear heating on VV shell showing poloidal manifold water from Blanket Module 01

Global Evaluation of Prompt Dose Rate during ITER Operation using Hybrid MCNP/Deterministic Method

Global Evaluation of Prompt Dose Rate during ITER Operation using Hybrid MCNP/Deterministic Method

ITER is the first integrated fusion test reactor. It is a joint international research and development project that aims to demonstrate the scientific and technical feasibility of fusion power. The partners in the project - the ITER Parties - are the European Union (represented by EURATOM), Japan, the People's Republic of China, India, the Republic of Korea, the Russian Federation and the U.S. ITER will be constructed in Europe, at Cadarache in the South of France.

The UW neutronics team has been involved in the ITER project since its inception in the late 1980s. Our numerous publications reflect our active involvement as we continue leading the US-ITER nuclear activities, offering a unique approach to model ITER and its subsystems using DAGMC that couples the CAD geometry directly with the 3-D MCNP code.

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ITER Newsline

Publications

Results: 81 to 117 of 117 order by: UWFDM Author↑ Title Date
1  2  3  

UWFDM-1007   Summary Report on the Neutronics Activities Performed by the U.S. Home Team as Part of the Blanket Design Task D202 in 1995; M.E. Sawan, H.Y. Khater, L.A. El-Guebaly, March 1996. (30 pages, 665 kB)

UWFDM-1056   Three-Dimensional Neutronics Analysis for the ITER Divertor Cassette; M.E. Sawan, November 1997 [also ITER/US/97-IV-DV-10]. (22 pages, 261 kB)

UWFDM-1077   Three-Dimensional Neutronics Analysis for the ITER Divertor Cassette Design Options; M.E. Sawan, R.T. Santoro, June 1998 [Presented at the 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN]. (8 pages, 294 kB)

retrieve PDF Three-Dimensional Neutronics Analysis for the ITER Divertor Cassette Design Options; M.E. Sawan, R.T. Santoro, June 1998 [Presented at the 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN]. (24 pages, 468 kB)

Three-Dimensional Neutronics Analysis for the US Magnet Shield of ITER; M.E. Sawan and L.A. El-Guebaly, May 1991 [Fusion Technology, Vol. 19, No. 3, Part 2B, 1469].

UWFDM-838   Three-Dimensional Neutronics Analysis for the US Magnet Shield of ITER; M.E. Sawan and L.A. El-Guebaly, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL; Fusion Tech. 19 (1991) 1469]. (9 pages, 602 kB)

UWFDM-839   Three-Dimensional Neutronics Analysis of the US Blanket Design for ITER; M.E. Sawan, Y. Gohar, H. Attaya, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL; Fusion Tech. 19 (1991) 1513]. (9 pages, 610 kB)

UWFDM-1030   Three-Dimensional Neutronics and Shielding Analyses for the ITER Divertor; M.E. Sawan, L. Petrizzi, R.T. Santoro, D. Valenza, June 1996 [Presented at the 12th Topical Meeting on the Technology of Fusion Power, 16-20 June 1996, Reno NV]. (7 pages, 588 kB)

Three-Dimensional Nuclear Analysis for the US Dual Coolant Lead Lithium ITER Test Blanket Module; M.E. Sawan, B. Smith, E.P. Marriott, P.P.H. Wilson, 2010 [Fusion Engineering and Design 85 (2010) 1027-1032].

UWFDM-1397   Three-Dimensional Nuclear Analysis for the US Dual Coolant Lead Lithium ITER Test Blanket Module; M.E. Sawan, B. Smith, E.P. Marriott, P.P.H. Wilson, December 2010 [published in Fusion Engineering and Design 85 (2010) 1027-1032].

retrieve PDF Three-Dimensional Nuclear Analysis for the US Dual Coolant Lithium Lead ITER Test Blanket Module; M. Sawan, B. Smith, E. Marriott, P. Wilson, October 2009 [presented at the 9th International Symposium on Fusion Nuclear Technology (ISFNT-9), 11-16 October 2009, Dalian, China]. (19 pages, 1.8 MB)

UWFDM-1380   Three-Dimensional Nuclear Analysis for the US Dual Coolant Lithium Lead ITER Test Blanket Module; M.E. Sawan, B. Smith, E.P. Marriott, P.P.H. Wilson, December 2010 [published in Fusion Engineering and Design, 85 (2010) 1027-1032]. (15 pages, 2.5 MB)

UWFDM-1393   Two-Dimensional Nuclear Analysis in Support of ITER Blanket Module Design; M.E. Sawan, May 2011. (13 pages, 1.4 MB)

retrieve PDF Updated DCLL TBM Neutronics Analysis; Mohamed Sawan, August 2008 [presented at the Fusion Nuclear Science and Technology (FNST) meeting, 12-14 August 2008, UCLA, Los Angeles CA]. (32 pages, 5.7 MB)

retrieve PDF 3-D Neutronics Analysis of the ITER First Wall/Shield Module 13; B. Smith, P.P.H. Wilson, M.E. Sawan, June 2007 [presented at the 22nd IEEE/NPSS Symposium on Fusion Engineering, 17-21 June 2007, Albuquerque NM]. (1 page, 5.8 MB)

UWFDM-1391   Robust Tracking and Advanced Geometry for Monte Carlo Radiation Transport; Brandon M. Smith, March 2011 [Ph.D. thesis]. (147 pages, 6.2 MB)

UWFDM-1389   Sealing Faceted Surfaces to Achieve Watertight CAD Models; B.M. Smith, T.J. Tautges, P.P.H. Wilson, October 2010 [Proceedings of the 19th International Meshing Roundtable, October 3-6, 2010, Chattanooga TN]. (20 pages, 1.2 MB)

retrieve PDF Sealing Faceted Surfaces to Achieve Watertight CAD Models; B.M. Smith, T.J. Tautges, P.P.H. Wilson, October 2010 [Proceedings of the 19th International Meshing Roundtable, 3-6 October 2010, Chattanooga TN]. (32 pages, 2.5 MB)

UWFDM-1349   Source Profile Analysis for the ITER First Wall/Shield Module 13; B. Smith, P. Wilson, M. Sawan and T. Bohm, September 2008 [presented at the 18th ANS Topical Meeting on Fusion Energy, 28 September-2 October 2008, San Francisco CA]. (7 pages, 1.7 MB)

retrieve PDF Source Profile Analysis for the ITER First Wall/Shield Module 13; B. Smith, P.P.H. Wilson, M. Sawan, T. Bohm, September 2008 [presented at the 18th ANS Topical Meeting on Fusion Energy, 28 September-2 October 2008, San Francisco CA]. (1 page, 14 MB)

UWFDM-1328   Three Dimensional Neutronics Analysis of the ITER First Wall/Shield Module 13; B. Smith, P.P.H. Wilson, M.E. Sawan, June 2007 [presented at the 22nd IEEE/NPSS Symposium on Fusion Engineering, 17-21 June 2007, Albuquerque NM]. (7 pages, 2.9 MB)

retrieve PDF Quantifying the Advantages of Counter Flow Helium First Wall Cooling: A Thermal-Hydraulic Comparison of ITER TBM First Wall Cooling Designs; G. Sviatoslavsky, M. Dagher, P. Calderoni, C.P.C. Wong, September 2005 [presented at the 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), 26-29 September 2005, Knoxville TN]. (1 page, 880 kB)

UWFDM-836   Mechanical Design and Fabrication of the U.S. Solid Breeder Blanket for ITER; I.N. Sviatoslavsky, J.P. Blanchard, Y. Gohar, S. Majumdar, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL]. (9 pages, 852 kB)

UWFDM-936   U.S. Aqueous Salt Blanket for ITER; I.N. Sviatoslavsky, M. Sawan, G.L. Kulcinski, J. Blanchard, L. El-Guebaly, L. Wittenberg, February 1989 [Presented at the U.S./Canada Workshop on Lithium Salt Blankets, Toronto, Canada, 7-9 February 1989]. (32 pages, 1.6 MB)

UWFDM-824   U.S. Aqueous Salt Blanket for ITER; I.N. Sviatoslavsky, M.E. Sawan, L.J. Wittenberg, G.L. Kulcinski, J.P. Blanchard, E.A. Mogahed, February 1990 [published in Fusion Engineering and Design 13 (1990) 33-4]. (28 pages, 4.2 MB)

UWFDM-969   Pulsed Activation Analyses of the ITER Blanket Design Options Considered in the Blanket Trade-Off Study; Q. Wang and D.L. Henderson, June 1994 [presented at the 3rd International Symposium on Fusion Nuclear Technology, June 26 - July 1, 1994, Los Angeles CA; to be published in Fusion Engineering and Design]. (22 pages, 710 kB)

UWFDM-977   Summary Report for ITER Design Task D10: Updating the Activation Code RACC for ITER Design Analysis; Qingming Wang and D.L. Henderson, January 1995 (revised April 1995). (29 pages, 737 kB)

UWFDM-930   MHD, Heat Transfer and Stress Analysis for the ITER Self-Cooled Blanket Design; X.R. Wang, E.A. Mogahed, I.N. Sviatoslavsky, October 1993. (29 pages, 1.5 MB)

State-of-the-Art 3-D Radiation Transport Methods for Fusion Energy Systems; P.P.H. Wilson, R. Feder, U. Fischer, M. Loughlin, L. Petrizzi, Y. Wu, and M. Youssef, 2008 [Fusion Engineering and Design, 83, 824 (2008)].

retrieve PDF Acceleration Techniques for the Direct Use of CAD-Based Geometry in Fusion Neutronics Analysis; P.P.H. Wilson, T.J. Tautges, J.A. Kraftcheck, B.M. Smith, D.L. Henderson, October 2009 [presented at the 9th International Symposium on Fusion Nuclear Technology (ISFNT-9), 11-16 October 2009, Dalian, China]. (29 pages, 1.4 MB)

retrieve PDF Innovations in 3-Dimensional Neutronics Analysis for Fusion Systems; P. Wilson, T. Tautges, M. Sawan, L. El-Guebaly, D. Henderson, G. Sviatoslavsky, B. Kiedrowski, A. Ibrahim, B. Smith, R. Slaybaugh, November 2006 [presented at the 17th ANS Topical Meeting on Fusion Energy, 13-15 November 2006, Albuquerque NM]. (27 pages, 4.2 MB)

retrieve PDF Nuclear Heating In Critical Components Of Alternative ITER First Wall Attachment Mechanism; P.P.H. Wilson, M.E. Sawan, E.P. Marriott, M.A. Ulrickson, May 2009 [presented at the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (1 page, 580 kB)

UWFDM-1367   Nuclear Heating in Critical Components of Alternative ITER First Wall Attachment Mechanism; P.P.H. Wilson, M.E. Sawan, E.P. Marriott, M.A. Ulrickson, May 2009 [prepared for the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (5 pages, 422 kB)

retrieve PDF Assessment of the Activation, Decay Heat, and Waste Disposal of a Dual Coolant Lithium Lead Test Blanket Module for ITER; M.Z. Youssef and M.E. Sawan, September 2005 [presented at the 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), 26-29 September 2005, Knoxville TN]. (1 page, 821 kB)

UWFDM-1279   Assessment of the Activation, Decay Heat, and Waste Disposal of a Dual Coolant Lithium Lead Test Blanket Module for ITER; M.Z. Youssef and M.E. Sawan, September 2005 [presented at the 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), 26-29 September 2005, Knoxville TN]. (8 pages, 1.2 MB)

UWFDM-1356   Nuclear Analyses for Two "Look-Alike" Helium-Cooled Pebble Bed Test Blanket Sub-Modules Proposed by the US for Testing in ITER; M.Z. Youssef, M.E. Sawan and A. Ying, February 2006 [published in Fusion Engineering and Design, 81 (2006) 1567-1576]. ( available online )

UWFDM-1248   On the Strategy and Requirements for Neutronics Testing in ITER; M.Z. Youssef and M.E. Sawan, September 2004 [Proceedings 16th ANS Topical Meeting on Fusion Energy, Fusion Science and Technology 47 (4), May 2005, pp. 1038-1045]. (11 pages, 947 kB)

Results: 81 to 117 of 117 order by: UWFDM Author↑ Title Date
1  2  3