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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.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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Latest News
Bipartisan Nuclear REFUEL Act introduced in the U.S. House
Peters
Latta
To streamline the licensing requirements for nuclear fuel recycling facilities and help increase investment in nuclear energy in the United States, U.S. Reps. Bob Latta (R., Ohio) and Scott Peters (D., Calif.) have introduced the bipartisan Nuclear REFUEL Act in the House of Representatives.
The bill, introduced on December 6, would amend the definition of “production facility” in the Atomic Energy Act, clarifying that a reprocessing facility producing uranium-transuranic mixed fuel would be licensed only under 10 CFR Part 70. According to the lawmakers, this single-step licensing process would significantly streamline the licensing requirements for fuel recycling facilities.
Liang-Che Dai, Chung-Yu Yang, Yng-Ruey Yuann, Bau-Shei Pei, Chun-Kuan Shih
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 96-103
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE14-145
Articles are hosted by Taylor and Francis Online.
According to “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants” (NUREG-0800) of the U.S. Nuclear Regulatory Commission, the homogeneous and thermal equilibrium critical flow model (HEM model) is acceptable for pressure and temperature analysis of the subcompartment of the containment. However, it was not built into the RELAP5-3D code. In order to provide the blowdown boundary conditions that meet the acceptance criteria for the subcompartment pressure and temperature response analysis, Institute of Nuclear Energy Research implemented and assessed the Moody HEM model of RELAP5-3D. The assessment phase was subsequent to the implementation of the Moody HEM model of RELAP5-3D. Three experiments of Marviken critical flow tests (CFTs) were selected as the assessment cases. They were CFT 15, CFT 22, and CFT 24. The assessment input decks of RELAP5-3D had been modified from the appendixes of the references. Additional comparisons with the results of the RELAP5-3D built-in Ransom-Trapp and Henry-Fauske critical flow models were also included. The comparisons of the calculated blowdown mass flow rate with the test data assessed the newly implemented model, which gave good prediction. Moreover, the comparisons between the results of the critical flow models of RELAP5-3D and the test data provided a measure of the relative conservatism of the critical flow calculations.