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-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)

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-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)

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)

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

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-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-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)

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

UWFDM-964   Shielding Analysis for the ITER Divertor and Vacuum Pumping Ducts; M.E. Sawan, Y. Gohar, R. Santoro, 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]. (19 pages, 683 kB)

UWFDM-939   Shielding Effectiveness of Candidate Structural Materials and Liquid Metal Coolants for the ITER Blanket; M.E. Sawan and L.A. El-Guebaly, January 1994 [prepared for the 8th International Conference on Radiation Shielding, April 24-28, 1994, Arlington TX]. (9 pages, 612 kB)

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-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-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)

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

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

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)

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)

UWFDM-923   A Complete Loss of Coolant Accident (LOCA) Analysis for the Inboard Component of ITER CDA; E.A. Mogahed, M.E. Sawan, H.Y. Khater, October 1993 [presented at 15th IEEE/NPSS Symposium on Fusion Engineering,. 11-14 October 1993, Hyannis MA]. (7 pages, 633 kB)

UWFDM-1020   ITER Limiter First Wall 3-D Thermo-Mechanical Analysis; E.A. Mogahed and I.N. Sviatoslavsky, May 1996 [Presented at the 12th Topical Meeting on the Technology of Fusion Power, 16-20 June 1996, Reno NV]. (7 pages, 727 kB)

UWFDM-832   Thermal Analysis of the Blanket and Shield for the U.S. ITER Design; E.A. Mogahed and I.N. Sviatoslavsky, October 1990 [Presented at the 9th Topical Meeting on the Technology of Fusion Energy, 7-11 October 1990, Oak Brook IL (Fus. Tech. 19 (3) Pt. 2A 1546-1551)]. (9 pages, 742 kB)

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