Rejuvenation of the CANDU Spent Fuel in (D-T)–Driven Hybrid Reactors
Author:
Affiliation:
1. Erciyes University Mühendislik Fakültesi Kayseri 38090, Turkey
Publisher
Informa UK Limited
Subject
General Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST98-A40
Reference35 articles.
1. Cm-244 as Multiplier and Breeder in a THO2Hybrid Blanket Driven by a (D,T) Source
2. Fission Power Flattening in Hybrid Blankets Using Mixed Fuel
3. Realization of a Flat Fission Power Density in a Hybrid Blanket Over Long Operation Periods
4. Power Flattening in a Catalyzed Deuterium-Deuterium Fusion-Driven Hybrid Blanket Using Nuclear Waste Actinides
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1. Numerical and Statistical Analysis of FR Spent Fuel Transmutation in a Thorium Fusion Breeder;Journal of Fusion Energy;2008-10-16
2. Monte Carlo calculation for various enrichment lithium coolant using different data libraries in a hybrid reactor;Energy Conversion and Management;2008-07
3. Monte Carlo calculation of radiation damage in first wall of an experimental hybrid reactor;Annals of Nuclear Energy;2007-11
4. Neutronic analysis of lithium hydride (LiH) material IN A (D, T) driven hybrid blanket;Journal of the Chinese Institute of Engineers;2007-01
5. Investigation of neutronic performance of a peaceful nuclear explosive reactor (PACER) evaluating UF4 and ThF4 nuclides;Sadhana;2004-08
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