Effect of mono-2-ethylhexylphosphoric acid on the extraction processing of a refinate of the regeneration of spent fuel cells of a water-moderated-water-cooled power reactor with di-2-ethylhexylphosphoric acid

1981 ◽  
Vol 51 (4) ◽  
pp. 637-638
Author(s):  
V. S. Smelov ◽  
B. A. Kondrat'ev ◽  
V. V. Chubukov ◽  
S. N. Dobromyslova
Keyword(s):  
Fuel Cells ◽  
Power Reactor ◽  
Spent Fuel

Extraction of americium, curium, strontium, and the rare earth elements from aqueous waste solutions of the reprocessing of spent fuel cells of VV�R reactors

1974 ◽  
Vol 37 (5) ◽  
pp. 1133-1137 ◽  
Author(s):  
V. B. Shevchenko ◽  
V. S. Smelov ◽  
A. G. Kozlov ◽  
V. V. Chubukov ◽  
V. P. Lanin ◽  
...  
Keyword(s):  
Rare Earth ◽  
Fuel Cells ◽  
Rare Earth Elements ◽  
Spent Fuel ◽  
Aqueous Waste ◽  
The Rare Earth

scholarly journals Cooling Period Calculation of Evolutionary Power Reactor Spent Fuel for Dry Management Safety

2016 ◽  
pp. 17-21
Author(s):  
M. I. Youssef ◽  
G. F. Sultan ◽  
F. Morsi Hassan
Keyword(s):  
Heat Load ◽  
Power Reactor ◽  
Computer Code ◽  
Normal Operation ◽  
Spent Fuel ◽  
Cooling Period ◽  
Decay Heat ◽  
Safety Margins ◽  
Epr Parameters

The calculation of the evolutionary power reactor (EPR) spent fuel (SF) cooling period (CP) was performed. The CP was determined by comparing the heat load of a cask with the calculated value of EPR decay heat (DH). The EPR DH was calculated by the ORIGEN computer code based on the EPR parameters. For conservatively study, the EPR and ORIGEN parameters that lead to higher DH values were selected and safety margins were considered. The fitting tool was utilized in the calculation of CP to overcome the ORIGEN limitation. The resultant values of CP will maintain the peak cladding temperature (PCT) of SF lower than 400°C during storage, transport, and disposal. The results show that -for normal operation- the SF of EPR should stay in the pool at least 4.75 years before it is loaded to the passively cooled dry casks.

Research of Shear Force during Spent Fuel Reprocessing Shearing Process

2014 ◽  
Vol 543-547 ◽  
pp. 533-536
Author(s):  
Yan Ru Fan ◽  
Xiang Jiang Wang ◽  
Hai Tao Huang
Keyword(s):  
Shear Force ◽  
Power Reactor ◽  
Sample Type ◽  
Spent Fuel ◽  
Engineering Construction ◽  
Experiment Verification ◽  
Spent Fuel Reprocessing ◽  
Research Experiment ◽  
Fuel Reprocessing ◽  
Abaqus Software

The process of a power reactor spent fuel reprocessing pilot plant had been completed after many years of scientific research experiment and engineering construction, while the commissioning results indicated that some technological problems exist in a few key equipments, especially the shearing machine. As the main design basis it is needed to obtain accurate shear force so as to improve research of shearing machine. In this paper, shearing fracture process and shear force have been simulated in ABAQUS software, also a sample type of shear machine has been realize to do the shearing experiment. Through the study, simulation result is verified reliable comparing with the experimental data and the research method using computer simulation combined with experiment verification is significance to the research of spent fuel reprocessing.

scholarly journals The Effects of U-233 Impurity on U-232 and Tl-208 Buildup in Experimental Power Reactor with Thorium-Based Fuel

2021 ◽  
Vol 2072 (1) ◽  
pp. 012001
Author(s):  
R A P Dwijayanto ◽  
Suwoto ◽  
Zuhair ◽  
Z Su’ud
Keyword(s):  
Fuel Cycle ◽  
Power Reactor ◽  
High Energy ◽  
Spent Fuel ◽  
Thorium Cycle ◽  
Gamma Emitter

Abstract The existence of Tl-208 in thorium fuel cycle is a double-edged sword. Tl-208 is a high-energy 2.6 MeV gamma emitter, which acts as an effective proliferation barrier while simultaneously complicating the handling of the spent fuel. To ensure the safety of the latter, the buildup of both Tl-208 and its parent, U-232, are necessary to be understood. This paper attempts to analyse the buildup of U-232 and Tl-208 in the Reaktor Daya Eksperimental (Experimental Power Reactor/RDE) fuel based on thorium cycle, using various U-233 isotopic vectors. The simulation result shows that U-232-contaminated fresh fuels ended up with higher Tl-208 and U-232 activities at the end of cycle (EOC) compared with uncontaminated fresh fuel. However, their U-232 build-up rate are lower and even negative at one case. Then, lower U-233 purity caused a higher U-232 and Tl-208 activities at EOC. This result implies a considerable difference of isotope buildup between the various U-233 vectors. Consequently, the thorium cycle-based RDE spent fuel handling should consider the isotopic vector of U-233 used in fresh fuel.

Prospective Power-Reactor Fuel Cycles Based on Water-Free Reprocessing of Spent Fuel

Atomic Energy ◽  
2004 ◽  
Vol 96 (5) ◽  
pp. 320-326 ◽  
Author(s):  
A. F. Grachev ◽  
A. A. Maershin ◽  
O. V. Skiba ◽  
V. A. Tsykanov ◽  
A. V. Bychkov ◽  
...  
Keyword(s):  
Power Reactor ◽  
Reactor Fuel ◽  
Spent Fuel ◽  
Fuel Cycles

scholarly journals NUCLIDES COMPOSITION OF EXPERIMENTAL POWER REACTOR (RDE) SPENT FUEL

2020 ◽  
Vol 22 (1) ◽  
pp. 9
Author(s):  
Kristina Kristina ◽  
Amir Hamzah ◽  
Muhammad Subekti ◽  
Menik Ariani
Keyword(s):  
Half Life ◽  
Power Reactor ◽  
Life Time ◽  
Total Activity ◽  
Future Research ◽  
Spent Fuel ◽  
Activity Data ◽  
Fuel Storage ◽  
Calculation Results ◽  
Loading Scheme

The management of spent fuel is an issue of safety for Indonesia in the phase of designing RDE. Several studies regarding spent fuel are limited by geometrical characteristics and number of nuclides library. Therefore, different methodologies utilizing MCNPX2.6.0 were applied to get better information for further research. In this study, a single fuel pebble containing UO2, was burned using 5 cycles of multi-pass loading scheme for 1080 days to obtain the same energy as RDE’s core, which is about 79.90 GWd/MTU. The multiplication factor k-inf decreased at each cycle and stopped at 1.14575. The calculation results in the nuclides composition of the spent fuel after 1080 days of burning and 5 years of cooling containing 241 nuclides consist of 21 actinides and 220 nonactinides. Actinides with the highest activity of 8.96 Ci is with mass of 0.0867 g, whose half-life time is 14 years long. Nonactinides with the highest activity of 4.47 Ci is  with mass of 0.0514 g, whose half-life time is 30.17 years long. The total activity of spent fuel pebble is 22.9 Ci with total mass of 5.28 g. The mass and activity data of each nuclide contained in the spent pebble will be used in the future research for performing safety analysis of the spent fuel storage tank.Keywords: Nuclides composition, Pebble, Spent fuel, RDE, MCNPX

scholarly journals Application of Power Reactors for Transmutation of Actinides

2004 ◽  
Author(s):  
B. R. Bergelson ◽  
A. S. Gerasimov ◽  
G. V. Tikhomirov
Keyword(s):  
Power Reactor ◽  
Storage Facility ◽  
Spent Fuel ◽  
Light Water ◽  
Water Power ◽  
Long Term Storage ◽  
Self Service ◽  
Reactor Operating ◽  
Term Storage

Heavy-water and light-water power reactors can be used for partial transmutation of radwaste. Such transmutation allows us to limit on relatively low level the radiotoxicity accumulated in long-term storage of spent fuel. At transmutation in PHWR-880 reactor operating in the mode of self-service, equilibrium radiotoxicity in storage facility and the time of its achievement are 4–5 times less than for the transmutation in power reactor VVER-1000.

scholarly journals CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL.

2019 ◽  
Vol 25 (2) ◽  
Author(s):  
R. Andika Putra Dwijayanto, S.T. ◽  
Ihda Husnayani ◽  
Zuhair Zuhair
Keyword(s):  
Power Reactor ◽  
Photon Emission ◽  
Radiation Shielding ◽  
Spent Fuel ◽  
Gamma Emission ◽  
Fuel Characteristics ◽  
Enriched Uranium ◽  
The Moment ◽  
Interim Storage ◽  
Thorium Cycle

CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL. There are several options of nuclear fuel utilisation in the HTGR-based Experimental Power Reactor (Reaktor Daya Eksperimental/RDE). Although mainly RDE utilises low enriched uranium (LEU)-based fuel, which is the most viable option at the moment, it is possible for RDE to utilise other fuel, for example thorium-based and possibly even plutonium-based fuel. Different fuel yields different spent fuel characteristics, so it is necessary to identify the characteristics to understand and evaluate their handling and interim storage. This paper provides the study on the characteristics of thorium-fuelled RDE spent fuel, assuming typical operational cycle. ORIGEN2.1 code is employed to determine the spent fuel characteristics. The result showed that at the end of the calculation cycle, each thorium-based spent fuel pebble generates around 0,627 Watts of heat, 28 neutrons/s, 8.28x1012 photons/s and yield 192.53 curies of radioactivity. These higher radioactivity and photon emission possibly necessitate different measures in spent fuel management, if RDE were to use thorium-based fuel. Tl-208 activity, which found to be emitting potentially non-negligible strong gamma emission, magnified the requirement of proper spent fuel handling especially radiation shielding in spent fuel cask.Keywords: RDE, spent fuel, thorium, HTGR, Tl-208.

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