ITER

ITER isometric

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

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

Detailed model of 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

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.

Publications

UWFDM-1083 Activation Analysis for the ITER Divertor Cassette; H.Y. Khater and M.E. Sawan, June 1998 [Presented at the 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN]. (6 pages, 177 kB)

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)

UWFDM-1257 US Plans and Strategy for ITER Blanket Testing; M. Abdou, D. Sze, C. Wong, M. Sawan, A. Ying, N. Morley, September 2004 [Proceedings 16th ANS Topical Meeting on Fusion Energy, Fusion Science and Technology 47 (3), April 2005, pp. 475-487]. (16 pages, 2.1 MB)

UWFDM-1274 Neutronics Features of a Dual Coolant Lithium Lead Test Blanket Module for ITER; M.E. Sawan and M.Z. Youssef, September 2005 [presented at the 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), 26-29 September 2005, Knoxville TN]. (7 pages, 863 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-1326 Neutronics Assessment of the ITER First Wall/Shield Modules; M.E. Sawan, B. Smith, P. Wilson, June 2007 [presented at the 22nd IEEE/NPSS Symposium on Fusion Engineering, 17-21 June 2007, Albuquerque NM]. (9 pages, 3.2 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)

UWFDM-1348 Radiation Streaming in Gaps Between ITER First Wall/Shield Modules; T.D. Bohm, M.E. Sawan, P. Wilson, September 2008 [presented at the 18th ANS Topical Meeting on Fusion Energy, 28 September-2 October 2008, San Francisco CA].

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)

UWFDM-1355 Physics and Technology Conditions for Attaining Tritium Self-Sufficiency for the DT Fuel Cycle; M.E. Sawan and M.A. Abdou, February 2006 [published in Fusion Engineering and Design, 81 (2006) 1131-1144]. ( available online )

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-1360 Neutronics Performance Parameters for the US Dual Coolant Lead Lithium ITER Test Blanket Module; M.E. Sawan, E.P. Marriott, M. Dagher, May 2009 [prepared for the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (6 pages, 1.7 MB)

UWFDM-1361 Benchmarking FENDL-2.1 with Impact of ENDF/B-VII.0 Release on Nuclear Heating and Damage; M.E. Sawan, May 2009 [prepared for the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (6 pages, 550 kB)

UWFDM-1363 Application of CAD-Neutronics Coupling to Geometrically Complex Fusion Systems; M.E. Sawan, P.P.H. Wilson, T. Tautges, L.A. El-Guebaly, D.L. Henderson, T.D. Bohm, E.P. Marriott, B. Kiedrowski, B. Smith, A. Ibrahim, R. Slaybaugh, May 2009 [prepared for the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (8 pages, 2.8 MB)

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)

UWFDM-1368 Assessment of Using the Surface Source Approach in 3-D Neutronics of Fusion Systems; T.D. Bohm, B. Smith, M.E. Sawan, P.P.H. Wilson, August 2009. (22 pages, 3.8 MB)

UWFDM-1376 Peaking in SS Nuclear Parameters at a Water Interface; T.D. Bohm, M.E. Sawan, B. Smith, P.P.H. Wilson, December 2009. (17 pages, 1.5 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-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)

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

UWFDM-1395 Improvements to the Helium Flow Path in the US DCLL ITER Test Blanket Module; E.P. Marriott, June 2011. (17 pages, 3.0 MB)

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].

UWFDM-1399 ITER Neutronics Modeling Using Hybrid Monte Carlo Deterministic and CAD-Based Monte Carlo Methods; A.M. Ibrahim, S.W. Mosher, T.M. Evans, D.E. Peplow, M.E. Sawan, P.P.H. Wilson, J.C. Wagner, T. Heltemes, July 2011 [published in Nuclear Technology Vol. 175 (July 2011) 251--258].

UWFDM-1400 Impact of FENDL-2.1 Updates on Nuclear Analysis of ITER and Other Fusion Systems; M.E. Sawan and T.D. Bohm, August 2011 [published in Journal of the Korean Physical Society, Vol. 59, No. 2, August 2011, pp. 1158-1161].

UWFDM-1411 Environmental Aspects of W-Based Components Employed in ITER, ARIES, and PPCS Fusion Designs; M. Desecures, L. El-Guebaly, June 2012. (34 pages, 1.9 MB)

U.S. Technical Report for the ITER Blanket/Shield; L.A. El-Guebaly et al., July 1990 [Part B ITER Report, ITER-TN-BL-5-0-6, Garching, Germany].

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].

Neutron Shielding and Its Impact on the ITER Machine Design; W. Daenner, L. El-Guebaly, M. Sawan, et al., Dec. 1991 [Fusion Engineering & Design, Vol. 16, Part A, 183].

ITER Shielding Analysis; R.T. Santoro, Y. Gohar, R. Parker, G. Shatalov, M. Sawan, and H. Khater, 1995 [Fusion Engineering & Design 27, 62].

ITER 3D Shielding Analysis and Afterheat Analysis for the Whole Machine and Cryostat Area; M. Sawan, L. El-Guebaly and H. Khater, 1995 [University of Wisconsin Fusion Technology Institute Report UWFDM-976].

Neutronics and Shielding Results of the U.S. ITER Blanket Trade-Off Study; M.E. Sawan and L.A. El-Guebaly, 1995 [Fusion Engineering and Design, 28, 551-558].

Shielding Analysis for the ITER Divertor and Vacuum Pumping Ducts; M. Sawan, Y. Gohar, and R.T. Santoro, 1995 [Fusion Engineering & Design 28, 429].

Activation Analysis for the Plasma Facing Component of ITER Divertor; H.Y. Khater, M. Sawan, and D.L. Henderson, Oct. 1997 [Proc. IEEE 17th Symposium on Fusion Engineering, San Diego, CA].

ITER Radiation Shielding and Neutronics Analysis; R.T. Santoro, H. Iida, V. Khripunov, M. Sawan, and T. Inoue, 1998 [Fusion Engineering & Design 39, 593].

Self-Shielding Effects in Decay Heat Calculations for Tungsten; M.E. Sawan, H.Y. Khater, H. Iida, R.T. Santoro, June 1998 [Presented at the 13th Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998, Nashville TN]. (12 pages, 254 kB)