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.

Related Links

ITER Newsline

Publications

Results: 1 to 40 of 117 order by: UWFDM Author↑ Title Date
1   2  3 

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-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)

retrieve PDF Assessment of the Surface Source Approach in 3-D Fusion Neutronics Analysis; T.D. Bohm, B. Smith, M.E. Sawan, P. Wilson, November 2010 [presented at the 19th ANS Topical Meeting on Fusion Energy, 7-11 November 2010, Las Vegas NV]. (1 page, 4.3 MB)

retrieve PDF Detailed 3-D Nuclear Analysis of ITER Blanket Modules; T.D. Bohm, M.E. Sawan, E.P. Marriott, P. Wilson, M. Ulrickson, J. Bullock, September 2013 [presented at the 11th International Symposium on Fusion Nuclear Technology, 16-20 September 2013, Barcelona, Spain]. (1 page, 1.7 MB)

Detailed 3-D Nuclear Analysis of ITER Blanket Modules; T.D. Bohm, M.E. Sawan, E.P. Marriott, P.P.H. Wilson, M. Ulrickson, J. Bullock, 2013 [Presented at 2013 ISFNT-11, to appear in Fusion Engineering & Design (2014)].

retrieve PDF Detailed Nuclear Analysis of ITER Blanket Modules (Work In Progress); T.D. Bohm, M.E. Sawan, S.T. Jackson, P. Wilson, September 2011 [presented at the 10th International Symposium on Fusion Nuclear Technology (ISFNT), 11-16 September 2011, Portland OR]. (1 page, 2.8 MB)

retrieve PDF Detailed Nuclear Analysis of ITER ELM Coils; T.D. Bohm, M.E. Sawan, S.T. Jackson, P. Wilson, September 2011 [presented at the 10th International Symposium on Fusion Nuclear Technology (ISFNT), 11-16 September 2011, Portland OR]. (1 page, 3.1 MB)

Detailed Nuclear Analysis of ITER ELM Coils; T.D. Bohm, M.E. Sawan, S.T. Jackson, and P.P.H. Wilson, 2012 [Fusion Engineering & Design, vol. 87, pp. 657-661 (2012)].

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 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)

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-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)

The Impact of Simplifications on 3-D Neutronics Analysis of Blanket Modules in ITER; T.D. Bohm, M.E. Sawan, and P.P.H. Wilson, September 2013 [Fusion Science & Technology, vol. 64, pp. 587-591 (September 2013)].

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-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)

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-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-940   Shielding Analysis for ITER with Impact of Assembly Gaps and Design Inhomogeneities; L.A. El-Guebaly and M.E. Sawan, January 1994 [prepared for the 8th International Conference on Radiation Shielding, April 24-28, 1994, Arlington TX]. (11 pages, 769 kB)

UWFDM-872   Shielding Considerations for ITER: Current Status and Future Directions; L.A. El-Guebaly, M.E. Sawan, December 1991 [presented at ``New Horizons in Radiation Protection and Shielding'', 26 April - 1 May 1992, Pasco WA.]. (11 pages, 781 kB)

UWFDM-811   Shielding Design Options for the TF Magnets of ITER; L.A. El-Guebaly, October 1989 [Presented at the 13th Symposium on Fusion Engineering, 2-6 October 1989, Knoxville TN; published in Proc. IEEE]. (7 pages, 523 kB)

UWFDM-774   Tungsten versus Steel in Inboard Shield of ITER: Impact on Magnet Damage, Reactor Size, and Cost; Laila A. El-Guebaly, Mohamed E. Sawan, October 1988 [presented at the 8th Topical Meeting on the Technology of Fusion Energy, 9-13 October 1988, Salt Lake City UT; Fusion Tech. 15, No. 2, Part 2B, 881 (1989)]. (9 pages, 870 kB)

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].

UWFDM-842   Potential for D-3He Operation in ITER; G.A. Emmert, December 1990. (19 pages, 649 kB)

retrieve PDF Global Evaluation of the Prompt Dose in ITER Using the Hybrid Monte Carlo/Deterministic Techniques; Ahmad Ibrahim, Scott Mosher, Thomas Evans, Douglas Peplow, Mohamed Sawan, Paul Wilson, John Wagner, November 2010 [presented at the 19th ANS Topical Meeting on Fusion Energy, 7-11 November 2010, Las Vegas NV]. (13 pages, 1.9 MB)

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].

retrieve PDF ITER Neutronics Modeling Using Hybrid Monte Carlo/Deterministic Techniques and CAD Based Monte Carlo; A.M. Ibrahim, S.W. Mosher, T.M. Evans, D.E. Peplow, M.E. Sawan, P.P.H. Wilson, J.C. Wagner, April 2010 [presented at the American Nuclear Society Radiation Protection and Shielding Division Topical Meeting, 19 April 2010, Las Vegas, NV]. (23 pages, 1.8 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)

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, 2011 [Nuclear Technology Vol. 175 (2011) 251-258].

UWFDM-966   Activation Analyses for the Different Options Considered in the U.S. ITER Blanket Trade-Off Study; H.Y. Khater, 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]. (16 pages, 511 kB)

UWFDM-777   Activation Analysis for the Aqueous Self-Cooled Blanket and Shield of ITER; H.Y. Khater, M.E. Sawan, S.W. Lomperski, I.N. Sviatoslavsky, October 1988 [presented at the 8th Topical Meeting on the Technology of Fusion Energy, 9-13 October 1988, Salt Lake City UT]. (9 pages, 876 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)

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-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-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)

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)

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-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)

Results: 1 to 40 of 117 order by: UWFDM Author↑ Title Date
1   2  3