scholarly journals idaho Accelerator Center Advanced Fuel Cycle Research

2011 ◽  
Author(s):  
Douglas Wells ◽  
Dan Dale
Keyword(s):  
Fuel Cycle ◽  
Advanced Fuel

scholarly journals Advanced Fuel Cycle Cost Basis

2009 ◽  
Author(s):  
D. E. Shropshire ◽  
K. A. Williams ◽  
W. B. Boore ◽  
J. D. Smith ◽  
B. W. Dixon ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Advanced Fuel

Thermal Evaluations for Next Generation Nuclear Plant Fuel Testing

Volume 4 ◽  
2004 ◽  
Author(s):  
Richard G. Ambrosek ◽  
Debbie J. Utterbeck ◽  
Brandon Miller
Keyword(s):  
Nuclear Reactor ◽  
Fuel Cycle ◽  
Nuclear Plant ◽  
Light Water Reactors ◽  
Next Generation ◽  
Preliminary Information ◽  
Advanced Fuel ◽  
Water Reactors ◽  
Test Reactor ◽  
Test Fuel

The DOE Advanced Fuel Cycle Initiative and Generation IV reactor programs are developing new fuel types for use in the current Light Water Reactors and future advanced reactor concepts. The Advanced Gas Reactor program is planning to test fuel to be used in the Next Generation Nuclear Plant (NGNP) nuclear reactor. Preliminary information for assessing performance of the fuel will be obtained from irradiations performed in the Advanced Test Reactor large “B” experimental facility.

Transport of High-Temperature Molten Salt Slurry for Pyro-Reprocessing

2009 ◽  
Author(s):  
Takatoshi Hijikata ◽  
Tadafumi Koyama
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Fission Products ◽  
Spent Fuel ◽  
Supply Tank ◽  
Transport Studies ◽  
Advanced Fuel ◽  
Inner Diameter ◽  
Porous Anode ◽  
Transport Tube

Pyro-reprocessing is one of the most promising technologies for advanced fuel cycle with favorable economic potential and intrinsic proliferation resistance. The development of transport technology for molten salt is a key issue in the industrialization of pyro-reprocessing. As for pure molten LiCl-KCl eutectic salt at approximately 773 K, we have already reported the successful results of transport using gravity and a centrifugal pump. However, molten salt in an electrorefiner mixes with insoluble fines when spent fuel is dissolved in porous anode basket. The insoluble consists of noble metal fission products, such as Pd, Ru, Mo, and Zr. There have been very few transport studies of a molten salt slurry (metal fines - molten salt mixture). Hence, transport experiments on a molten salt slurry were carried out to investigate the behavior of the slurry in a tube. The apparatus used in the transport experiments on a molten salt slurry consisted of a supply tank, a 10° inclined transport tube (10 mm inner diameter), a valve, a filter, and a recovery tank. Stainless steel (SS) fines with diameters from 53 to 415 μm were used. To disperse these fines homogenously, the molten salt and fines were stirred in the supply tank by an impeller at speeds from 1200 to 2100 rpm. The molten salt slurry containing 0.2 to 0.4 vol.% SS fines was transported from the supply tank to the recovery tank through the transportation tube. In the recovery tank, the fines were separated from the molten salt by the filter to measure the transport behavior of molten salt and SS fines. When the velocity of the slurry was 0.02 m/s, only 1% of the fines were transported to the recovery tank. On the other hand, most of the fines were transported when the velocity of the slurry was more than 0.6 m/s. Consequently, the molten salt slurry can be transported when the velocity is more than 0.6 m/s.

scholarly journals Multiple Tier Fuel Cycle Studies for Waste Transmutation

2002 ◽  
Author(s):  
R. N. Hill ◽  
T. A. Taiwo ◽  
J. A. Stillman ◽  
D. J. Graziano ◽  
D. R. Bennett ◽  
...  
Keyword(s):  
Mass Flow ◽  
System Performance ◽  
Fuel Cycle ◽  
Department Of Energy ◽  
Waste Streams ◽  
Fuel Processing ◽  
Advanced Fuel ◽  
Support Ratio ◽  
Plutonium Separation ◽  
The U.S

As part of the U.S. Department of Energy Advanced Accelerator Applications Program, a systems study was conducted to evaluate the transmutation performance of advanced fuel cycle strategies. Three primary fuel cycle strategies were evaluated: dual-tier systems with plutonium separation, dual-tier systems without plutonium separation, and single-tier systems without plutonium separation. For each case, the system mass flow and TRU consumption were evaluated in detail. Furthermore, the loss of materials in fuel processing was tracked including the generation of new waste streams. Based on these results, the system performance was evaluated with respect to several key transmutation parameters including TRU inventory reduction, radiotoxicity, and support ratio. The importance of clean fuel processing (∼0.1% losses) and inclusion of a final tier fast spectrum system are demonstrated. With these two features, all scenarios capably reduce the TRU and plutonium waste content, significantly reducing the radiotoxicity; however, a significant infrastructure (at least 1/10 the total nuclear capacity) is required for the dedicated transmutation system.

scholarly journals Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development

2011 ◽  
Vol 59 (2(3)) ◽  
pp. 1207-1212
Author(s):  
M. E. Dunn ◽  
H. Derrien ◽  
L. C. Leal ◽  
C. Gil ◽  
D. Kim
Keyword(s):  
Data Analysis ◽  
Fuel Cycle ◽  
Resonance Region ◽  
Nuclear Data ◽  
Advanced Fuel

Analysis of Environmental Friendliness of Advanced Nuclear Fuel Cycle in Korea

2003 ◽  
Author(s):  
Yong Han Kim ◽  
Kun Jai Lee ◽  
Won Zin Oh
Keyword(s):  
Waste Management ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Clean Energy ◽  
Nuclear Fuel Cycle ◽  
Utilization Efficiency ◽  
High Level Waste ◽  
Environmental Friendliness ◽  
Fuel Cycles ◽  
Advanced Fuel

In order to show that the nuclear energy could be a clean energy, radioactive waste management, especially high level waste has to be successfully managed and also accepted by the public. As discussed, progressed and focused at GEN IV international project, reduction of long lived actinide source term and corresponding toxicity through transmutation process has been recognized as one possible solution to the problem and draw lots of attention these days and active R&D efforts are pursued and progressed worldwidely. Especially, much of interest has been initiated to the accelerator driven system (ADS) for the transmutation of the actinide as a subcritical reactors or combination to fast reactor (FR) to generate energy and transmute the HLW simultaneously in a cleaner and safer ways. This study compare and clarifies the roles and merits of the FR and ADS, which would be expected to be introduced into the future Korean nuclear fuel cycle partly, in view of environmental friendliness especially with the existing nuclear fuel cycle dominated by PWR in Korea. After selecting the most plausible and appropriate reactor strategy scenario, the mass flow balance of active radionuclides from ore to waste for several cases of advanced nuclear fuel cycle (where “advanced nuclear fuel cycle” means the nuclear fuel cycle with FR or ADS) is analyzed by computer code. Advanced nuclear fuel cycle with only FR or ADS, and with both FR and ADS were considered for this analysis. A spread sheet type of code, that compute material flow and some environmental friendliness indices chronologically, was developed and analyzed for the calculation. Some indices for the environmental friendliness (i.e. amount of actinide nuclides, radioactivity and radiotoxicity of them, and uranium resource requirement) for several types of advanced nuclear fuel cycles are analyzed comparing with those of once-through fuel cycle. According to the final results, it confirmed quantitatively that the advanced fuel cycle with FRs and ADSs would be one of the possible alternatives to relieve the burden of HLW waste management because those fuel cycle options might reduce the generation of the transuranic radionuclides by tens to hundreds times less compared to that of once-through fuel cycle. Especially advanced nuclear system combined with FR and ADS shows much better effects compared to not combined system. Resource utilization efficiency is also much upgraded high by the introduction of advanced fuel cycles with a significant high share of fast reactors (i.e. only a half amount of uranium can be consumed in case of introduction of breakeven type FR compared to once-through fuel cycle case.)

Advanced Fuel CANDU Reactor (AFCR) Core Physics With High-Burnup Recycled Uranium and Uranium-Thorium Fuel

2013 ◽  
Author(s):  
Mustapha Boubcher ◽  
Zhiliang Meng ◽  
Catherine M. Cottrell ◽  
Sermet Kuran
Keyword(s):  
Alternative Fuels ◽  
Fuel Cycle ◽  
Minimal Risk ◽  
Spent Fuel ◽  
Fuel Cycles ◽  
Fuel Bundle ◽  
Short Run ◽  
Advanced Fuel ◽  
Enriched Uranium ◽  
High Neutron

The CANDU reactor has flexibility for using alternative fuels, such as Recycled Uranium (RU), low-enriched uranium and thorium (LEU/Th) and plutonium-thorium (Pu/Th) based fuels. This capability results from a versatile pressure tube design, simple fuel bundle, on-power refuelling, and high neutron economy. The Advanced Fuel CANDU Reactor (AFCR), which retains the excellent neutron economy and fuel cycle flexibility that are inherent in the CANDU reactor design, is a design jointly undertaken by Candu Energy and its Chinese partners led by CNNC. The objective is to use RU that is planned to be available from the reprocessing of Chinese LWR fleet spent fuel and increase the overall uranium utilization at minimal cost and minimal risk at commercially proven CANDU type new build reactors. This paper is focused on various physics aspects of using RU and LEU/Th in the AFCR units in the short run. It also describes full-core management simulations for the implementation of DRU and LEU/Th fuel cycles in AFCR reactor. The CANFLEX bundle design was chosen as carrier for both DRU and LEU/Th fuel in this study.

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