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

UWFDM-976   1994 Summary Report for ITER Design Task D4. Shielding 3D Analysis. Afterheat Analysis for the Whole Machine and Cryostat Area. Part A: Neutronics and Shielding; M.E. Sawan, L.A. El-Guebaly, H.Y. Khater, January 1995. (30 pages, 859 kB)

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)

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)

retrieve PDF Acceleration Techniques for the Direct Use of CAD-Based Geometry in Fusion Neutronics Analysis; P.P.H. Wilson, T.J. Tautges, J.A. Kraftcheck, B.M. Smith, D.L. Henderson, October 2009 [presented at the 9th International Symposium on Fusion Nuclear Technology (ISFNT-9), 11-16 October 2009, Dalian, China]. (29 pages, 1.4 MB)

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-813   An Aqueous Lithium Salt Blanket for ITER; M.E. Sawan, I.N. Sviatoslavsky, G.L. Kulcinski, J.P. Blanchard, H.Y. Khater, E.A. Mogahed, L.J. Wittenberg, October 1989 [Presented at the 13th Symposium on Fusion Engineering, 2-6 October 1989, Knoxville TN; IEEE Cat. No. 89CH2820-9, Vol. 1, 74]. (7 pages, 607 kB)

UWFDM-775   An Aqueous Lithium Salt Self-Cooled Blanket and Shield for ITER; M.E. Sawan, I.N. Sviatoslavsky, G.L. Kulcinski, October 1988 [presented at the 8th Topical Meeting on the Technology of Fusion Energy, 9-13 October 1988, Salt Lake City UT; Fus. Tech. 15/2 (1989) 643]. (9 pages, 824 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-1006   Application of FENDL Nuclear Data to ITER Neutronics and Shielding Analyses; M.E. Sawan, March 1996 [Presented at the 1996 Radiation Protection and Shielding Topical Meeting, North Falmouth, MA, April 21-25, 1996]. (11 pages, 487 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-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 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)

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)

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)

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)

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)

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 ELM Coils: Nuclear Environment and Shielding Issues; M.E. Sawan and T. Bohm, February 2010 [presented at the ITER Neutronics Meeting, 8-9 February 2010, Aix-en-Provence, France]. (20 pages, 2.0 MB)

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)

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)

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].

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-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].

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].

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)

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].

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

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)

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