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: 41 to 80 of 117 order by: UWFDM Author Title↓ Date
1  2   3 

UWFDM-1024   Radiological Dose Rate Calculations for the International Thermonuclear Experimental Reactor (ITER); H.Y. Khater and R.T. Santoro, June 1996 [Presented at the 12th Topical Meeting on the Technology of Fusion Power, 16-20 June 1996, Reno NV]. (8 pages, 615 kB)

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].

retrieve PDF 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]. (1 page, 1.7 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-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-842   Potential for D-3He Operation in ITER; G.A. Emmert, December 1990. (19 pages, 649 kB)

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-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-827   Overview of the US-ITER Magnet Shield: Concept and Problems; 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, No. 3, Part 2B, 1475 (1991)]. (9 pages, 667 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-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-1051   Nuclear Heating and Damage Profiles in the ITER Divertor Cassette; M.E. Sawan and R.T. Santoro, September 1997 [Presented at the 17th IEEE/NPSS Symposium on Fusion Engineering, 6-10 October 1997, San Diego CA]. (6 pages, 163 kB)

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)

retrieve PDF Nuclear Analysis of ITER In-Vessel Coils; T.D. Bohm and M.E. Sawan, September 2010 [presented at the 26th Symposium on Fusion Technology (SOFT), 27 September-1 October 2010, Porto, Portugal]. (1 page, 178 kB)

retrieve PDF Nuclear Analysis in Support of ITER Blanket Modules Design; Mohamed E. Sawan, June 2011 [presented at the 24th Symposium on Fusion Engineering (SOFE), 26-30 June 2011, Chicago IL]. (1 page, 368 kB)

retrieve PDF Nuclear Analysis at UW in Support ITER Design; M.E. Sawan, P. Wilson, B. Smith, T. Bohm, February 2010 [presented at the ITER Neutronics Meeting, 8-9 February 2010, Aix-en-Provence, France]. (44 pages, 2.6 MB)

retrieve PDF Nuclear Analysis Capabilities for Fusion Energy Systems; A. Ibrahim, R. Slaybaugh, B. Smith, B. Kiedrowski, March 2007 [presented at the 2007 ANS Student Conference, Oregon State University, Corvallis OR, 29-31 March 2007]. (1 page, 4.8 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 )

retrieve PDF Next Step Options (NSO) Project Update FIRE/ITER; Mohamed Sawan, September 9, 2003 [FTI Tuesday meeting]. (29 pages, 403 kB)

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].

UWFDM-963   Neutronics and Shielding Results of the U.S. ITER Blanket Trade-Off Study; M.E. Sawan and L.A. El-Guebaly, 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]. (18 pages, 513 kB)

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)

retrieve PDF Neutronics Performance Parameters for the US Dual Coolant Lead Lithium ITER Test Blanket Module; M.E. Sawan, E.P. Marriott, M. Dagher, May 2009 [presented at the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (1 page, 2.7 MB)

UWFDM-1057   Neutronics Parameters in the Divertor Diagnostic Cassette of ITER; M.E. Sawan, November 1997 [also ITER/US/97-IV-DV-11]. (17 pages, 202 kB)

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)

retrieve PDF 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]. (1 page, 1.4 MB)

retrieve PDF Neutronics Assessment of the ITER First Wall/Shield Modules; M. Sawan, B. Smith, P. Wilson, June 2007 [presented at the 22nd IEEE/NPSS Symposium on Fusion Engineering (SOFE07), 17-21 June 2007, Albuquerque NM]. (27 pages, 3.7 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)

Neutronics Analysis of ITER Blanket Modules with Impact on Vacuum Vessel Shielding; M.E. Sawan, T.D. Bohm, and M.A. Ulrickson, September 2013 [Fusion Science & Technology, vol. 64, pp. 555-562 (September 2013)].

Neutronics Analysis in Support of the Fusion Development Facility Design Evolution; M.E. Sawan, A.M. Ibrahim, P.P.H. Wilson, E.P. Marriott, R.D. Stambaugh, and C.P.C. Wong, 2011 [Fusion Science & Technology, vol. 60, pp. 671-675 (2011)].

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].

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-868   Magnet Shielding Effectiveness of the Proposed Blankets for ITER; L.A. El-Guebaly, September 1991 [Presented at the 14th IEEE/NPSS Symposium on Fusion Engineering, 30 September - 3 October 1991, San Diego CA; published in Proc. IEEE]. (6 pages, 547 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)

retrieve PDF Investigation of Observed Peaking in Nuclear Parameters at Steel/Water Interfaces; T.D. Bohm, M.E. Sawan, B. Smith, P. Wilson, November 2010 [presented at the 19th ANS Topical Meeting on Fusion Energy, 7-11 November 2010, Las Vegas NV]. (1 page, 1.8 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)

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)

retrieve PDF Improved Geometrical Design of the US DCLL ITER Test Blanket Module; E. Marriott, M. Dagher, M. Sawan, C. Wong, June 2011 [presented at the 24th Symposium on Fusion Engineering (SOFE), 26--30 June 2011, Chicago IL]. (1 page, 2.8 MB)

retrieve PDF Impact of FENDL-2.1 Updates on Nuclear Analysis of ITER and Other Fusion Systems; M.E. Sawan and T.D. Bohm, April 2010 [presented at the International Conference on Nuclear Data for Science and Technology 2010 (ND2010), 26-30 April 2010, Jeju, Korea]. (1 page, 1.1 MB)

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].

Results: 41 to 80 of 117 order by: UWFDM Author Title↓ Date
1  2   3