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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
Fusion Science and Technology
Study indicates pilot facility could significantly reduce waste volumes
Waste disposal start-up Deep Isolation and fusion tech company SHINE Technologies have announced the completion of a collaborative study assessing the costs of disposing of radioactive byproducts from a pilot spent nuclear fuel recycling facility.
Indrajeet Singh, S. B. Degweker, Amod Kishore Mallick, Anurag Gupta
Nuclear Science and Engineering | Volume 193 | Number 8 | August 2019 | Pages 868-883
Technical Paper | doi.org/10.1080/00295639.2019.1576453
Articles are hosted by Taylor and Francis Online.
In a recent paper, we described the development of a method for calculating exact collision probabilities between different regions (namely, fuel kernels, graphite matrix, moderator, and coolant) of a lattice cell of a high temperature reactor (HTR) of the pebble bed variety. The method was shown to adequately represent the double heterogeneity in such reactors. In the present paper, we use some of the results obtained in that paper to construct a fast Monte Carlo algorithm for treatment of HTRs. This paper discusses the theoretical basis of the Monte Carlo algorithm, its implementation for the case of a lattice cell with the energy variable treated using a multigroup library, and results obtained. The method can be easily extended to full-core calculations using point cross-section data.