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 

retrieve PDF Benchmarking FENDL-2.1 with Impact of ENDF/B-VII.0 Release on Nuclear Heating and Damage; M.E. Sawan, May 2009 [presented at the 23rd Symposium on Fusion Engineering (SOFE), May 31-June 5, 2009, San Diego CA]. (1 page, 1.7 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)

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 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)

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 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)

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)].

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-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)

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)

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)

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)

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 Status of the ITER Project and Neutronics Activities; Mohamed Sawan, November 2006 [presented at the Cross Section Evaluation Working Group (CSEWG) Meeting, 6-7 November 2006, Brookhaven National Laboratory, Long Island NY]. (23 pages, 6.5 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-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-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-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 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)

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 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-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-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)

retrieve PDF ITER Test Blanket Module Program; M.E. Sawan, December 9, 2003 [FTI Tuesday meeting]. (24 pages, 3.2 MB)

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

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-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)

UWFDM-1075   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]. (6 pages, 196 kB)

retrieve PDF 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)

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)

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

UWFDM-1058   Three-Dimensional Activation Analysis for the ITER Divertor Cassette; H.Y. Khater and M.E. Sawan, November 1997 [also ITER/US/97-IV-DV-12]. (73 pages, 867 kB)

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-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-1052   3-D Thermo-Mechanical Analysis of the ITER Limiter Small Scale Specimen; E.A. Mogahed and I.N. Sviatoslavsky, October 1997 [Presented at the 17th IEEE/NPSS Symposium on Fusion Engineering, 6-10 October 1997, San Diego CA]. (6 pages, 279 kB)

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].

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)

UWFDM-1042   Summary Report on Work Performed in the Divertor Design Task D308, Subtask 10: Neutronics and Shielding Support Analyses of the ITER Divertor; M.E. Sawan, February 1997 [also ITER/US/96/IV-DV-21]. (22 pages, 261 kB)

UWFDM-1041   Application of the Processed FENDL Libraries to the Calculational Benchmark and ITER Design; M.E. Sawan, February 1997 [presented at the IAEA Advisory Group Meeting on ``Extension and Improvement of the FENDL Library for Fusion Applications,'' Vienna, Austria, 3-7 March 1997]. (18 pages, 162 kB)

UWFDM-1037   3-D Thermo-Mechanical Analysis of the ITER Limiter Small Scale Specimen; E.A. Mogahed and I.N. Sviatoslavsky, December 1996. (17 pages, 4.6 MB)

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