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-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-977   Summary Report for ITER Design Task D10: Updating the Activation Code RACC for ITER Design Analysis; Qingming Wang and D.L. Henderson, January 1995 (revised April 1995). (29 pages, 737 kB)

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)

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-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-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-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-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-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)

UWFDM-936   U.S. Aqueous Salt Blanket for ITER; I.N. Sviatoslavsky, M. Sawan, G.L. Kulcinski, J. Blanchard, L. El-Guebaly, L. Wittenberg, February 1989 [Presented at the U.S./Canada Workshop on Lithium Salt Blankets, Toronto, Canada, 7-9 February 1989]. (32 pages, 1.6 MB)

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)

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

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-824   U.S. Aqueous Salt Blanket for ITER; I.N. Sviatoslavsky, M.E. Sawan, L.J. Wittenberg, G.L. Kulcinski, J.P. Blanchard, E.A. Mogahed, February 1990 [published in Fusion Engineering and Design 13 (1990) 33-4]. (28 pages, 4.2 MB)

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-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-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-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-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)

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 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)

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)].

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)].

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 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)

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 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)

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].

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)].

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 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 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)

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