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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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Nuclear Science and Engineering
Fusion Science and Technology
Fusion energy radwaste management considerations
The question of what to do with the radioactive waste has been raised frequently for both fission and fusion. In the 1970s, fusion adopted the land-based disposal option, primarily based on the Nuclear Regulatory Commission’s decision to regulate all radioactive wastes as only a disposal issue, following the fission guidelines. In the early 2000s, members of the Advanced Research Innovation and Evaluation Study (ARIES) national team became increasingly aware of the high amount of mildly radioactive materials that 1-GWe fusion power plants will generate, compared with the current line of fission reactors. The main concern is that such a sizable inventory of mostly tritiated radioactive materials would tend to rapidly fill U.S. repositories—a serious issue that was overlooked in early fusion studies1 that could influence the public acceptability of fusion energy and will certainly become more significant in the immediate future if left unaddressed, as fusion moves toward commercialization.
Matjaz Ravnik, Tomaz Zagar, Andreja Persic
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 35-45
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A3012
Articles are hosted by Taylor and Francis Online.
Calculations of fuel element burnup for realistic mixed core conditions in a 250-kW TRIGA Mark II reactor are presented. Two types of fuel elements are considered: 70% enriched FLIP and 20% enriched standard fuel elements. Two calculation models are compared. The first is based on a one-dimensional two-group diffusion approximation (the TRIGAP computer code), and the second is based on a two-dimensional four-group diffusion equation (the TRIGLAV computer code). In both cases the unit-cell group constants are generated with the WIMS code. Results of the calculations are intercompared to evaluate the influence of the two-dimensional effects on fuel element burnup. The following two-dimensional effects are considered: mixed rings, in-core water gaps, vicinity of control rods, and asymmetric core loading patterns. Relative differences in fuel element burnup of 10% on average and up to 80% in extreme cases are observed because of the two-dimensional effects. The accuracy of the calculation is estimated also by comparing the calculated results to the measurements using the reactivity method.