scholarly journals Spent fuel assembly hardware: Characterization and 10 CFR 61 classification for waste disposal: Volume 2, Calculated activity profiles of spent nuclear fuel assembly hardware for pressurized water reactors

1989 ◽  
Author(s):  
S Short ◽  
A Luksic ◽  
T Lotz ◽  
M Schutz
Keyword(s):  
Fuel Assembly ◽  
Nuclear Fuel ◽  
Waste Disposal ◽  
Spent Nuclear Fuel ◽  
Pressurized Water Reactors ◽  
Spent Fuel ◽  
Pressurized Water ◽  
Nuclear Fuel Assembly ◽  
Water Reactors

scholarly journals Analyzing Design Considerations for Disassembly of Spent Nuclear Fuel during Head-End Process of Pyroprocessing

2020 ◽  
Vol 2020 ◽  
pp. 1-13
Author(s):  
Young-Hwan Kim ◽  
Yung-Zun Cho
Keyword(s):  
Fuel Assembly ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Scale Up ◽  
High Heat ◽  
Spent Fuel ◽  
Pressurized Water ◽  
Design Considerations ◽  
Nuclear Fuel Assembly ◽  
Cutting Processes

We have developed a practical-scale dry disassembling process to dismantle PWR (Pressurized Water Reactor) spent nuclear fuel assembly in the order of several tens of kilograms of heavy metal/batch to supply rod-cuts (cladding tube and UO2 pellets) for mechanical decladding process. Dry head-end disassembling process has advantages over the wet head-end process because of the lower risk of proliferation and treatment of spent fuel with relatively high heat and radioactivity. This study describes the main design considerations for the disassembling process of the spent nuclear fuel assembly during the dry head-end process. The down-ender, dismantling, extraction, and cutting technologies are analyzed and models have been designed for testing. The purpose of dry head-end disassembly process is to test the main device performance and to obtain scale-up data for practical-scale disassembling. With this in mind, design considerations were analyzed based on remoteness, and basic verification tests were performed. However, the authors used simulated fuel, instead of the actual spent fuel, owing to a lack of joint determination. In addition, in the present study, we did not consider the heat generated from minor actinides or the radioactivity of the fission product; these aspects will be considered in a future study. During the basic test performed in this study, a simulated assembly was completely disassembled using new methods, such as dismantling, extraction, and cutting processes. The practical-scale dry disassembling technology can be tested using scale-up data for reuse of the spent fuel.

Distributions of radionuclides on and in spent nuclear fuel claddings of pressurized water reactors

1990 ◽  
Vol 174 (1) ◽  
pp. 45-52 ◽  
Author(s):  
T. Hirabayashi ◽  
T. Sato ◽  
C. Sagawa ◽  
N.M. Masaki ◽  
M. Saeki ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Pressurized Water Reactors ◽  
Pressurized Water ◽  
Water Reactors

scholarly journals Assessment of the Radiotoxicity of Spent Nuclear Fuel from a Fleet of PWR Reactors

Energies ◽  
2021 ◽  
Vol 14 (11) ◽  
pp. 3094
Author(s):  
Mikołaj Oettingen
Keyword(s):  
Isotopic Composition ◽  
Nuclear Fuel ◽  
Nuclear Power ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Spent Fuel ◽  
Pressurized Water ◽  
Hybrid Energy ◽  
Cycle Simulation ◽  
Water Reactors

The paper presents the methodology for the estimation of the long-term actinides radiotoxicity and isotopic composition of spent nuclear fuel from a fleet of Pressurized Water Reactors (PWR). The methodology was developed using three independent numerical tools: the Spent Fuel Isotopic Composition database, the Nuclear Fuel Cycle Simulation System and the Monte Carlo Continuous Energy Burnup Code. The validation of spent fuel isotopic compositions obtained in the numerical modeling was performed using the available experimental data. A nuclear power embarking country benchmark was implemented for the verification and testing of the methodology. The obtained radiotoxicity reaches the reference levels at about 1.3 × 105 years, which is common for the PWR spent nuclear fuel. The presented methodology may be incorporated into a more versatile numerical tool for the modeling of hybrid energy systems.

scholarly journals Non-Proliferative, Thorium-Based, Core and Fuel Cycle for Pressurized Water Reactors

2009 ◽  
Author(s):  
Gilad Raitses ◽  
Michael Todosow ◽  
Alex Galperin
Keyword(s):  
Fuel Assembly ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Pressurized Water Reactors ◽  
Pressurized Water Reactor ◽  
Spent Fuel ◽  
Fuel Management ◽  
Pressurized Water ◽  
Water Reactors ◽  
Proliferation Potential

Two of the major barriers to the expansion of worldwide adoption of nuclear power are related to proliferation potential of the nuclear fuel cycle and issues associated with the final disposal of spent fuel. The Radkowsky Thorium Fuel (RTF) concept proposed by Professor A. Radkowsky offers a partial solution to these problems. The main idea of the concept is the utilization of the seed-blanket unit (SBU) fuel assembly geometry which is a direct replacement for a “conventional” assembly in either a Russian pressurized water reactor (VVER-1000) or a Western pressurized water reactor (PWR). The seed-blanket fuel assembly consists of a fissile (U) zone, known as seed, and a fertile (Th) zone known as blanket. The separation of fissile and fertile allows separate fuel management schemes for the thorium part of the fuel (a subcritical “blanket”) and the “driving” part of the core (a supercritical “seed”). The design objective for the blanket is an efficient generation and in-situ fissioning of the U233 isotope, while the design objective for the seed is to supply neutrons to the blanket in a most economic way, i.e. with minimal investment of natural uranium. The introduction of thorium as a fertile component in the nuclear fuel cycle significantly reduces the quantity of plutonium production and modifies its isotopic composition, reducing the overall proliferation potential of the fuel cycle. Thorium based spent fuel also contains fewer higher actinides, hence reducing the long-term radioactivity of the spent fuel. The analyses show that the RTF core can satisfy the requirements of fuel cycle length, and the safety margins of conventional pressurized water reactors. The coefficients of reactivity are comparable to currently operating VVER’s/PWR’s. The major feature of the RTF cycle is related to the total amount of spent fuel discharged for each cycle from the reactor core. The fuel management scheme adopted for RTF core designs allows a significant decrease in the amount of discharged spent fuel, for a given energy production, compared with standard VVER/PWR. The total Pu production rate of RTF cycles is only 30% of standard reactor. In addition, the isotopic compositions of the RTF’s and standard reactor grade Pu are markedly different due to the very high burnup accumulated by the RTF spent fuel.

Neutronic Analysis of Accident-Tolerant Fuel Assemblies With Silicon Carbide Cladding in Pressurized Water Reactors

2017 ◽  
Author(s):  
Zhixiong Tan ◽  
Jiejin Cai
Keyword(s):  
Silicon Carbide ◽  
Fuel Assembly ◽  
Power Distribution ◽  
Safety Margin ◽  
Severe Accident ◽  
Pressurized Water Reactors ◽  
Fuel Pellet ◽  
Pressurized Water ◽  
Neutronic Parameters ◽  
Water Reactors

After Fukushima Daiichi Nuclear Power Plant accident, alternative fuel-design to enhance tolerance for severe accident conditions becomes particularly important. Silicon carbide (SiC) cladding fuel assembly gain more safety margin as novel accident tolerant fuel. This paper focuses on the neutron properties of SiC cladding fuel assembly in pressurized water reactors. Annular fuel pellet was adopted in this paper. Two types of silicon carbide assemblies were evaluated via using lattice calculation code “dragon”. Type one was consisted of 0.057cm SiC cladding and conventional fuel. Type two was consisted of 0.089cm SiC cladding and BeO/UO2 fuel. Compared the results of SiC cladding fuel assembly neutronic parameters with conventional Zircaloy cladding fuel assembly, this paper analyzed the safety of neutronic parameters performance. Results demonstrate that assembly-level reactivity coefficient is kept negative, meanwhile, the numerical value got a relatively decrease. Other parameters are conformed to the design-limiting requirement. SiC kinds cladding show more flat power distribution. SiC cases also show the ability of reducing the enrichment of fuel pellets even though it has higher xenon concentration. These types of assembly have broadly agreement neutron performance with the conventional cladding fuel, which confirmed the acceptability of SiC cladding in the way of neutron physics analysis.

Comparative Stress Analyses of Dropped Spent Nuclear Fuel Assembly in a Prototypal Cask

2021 ◽  
Author(s):  
SAEHANSOL KANG ◽  
Donghyun Kim ◽  
Yoon-suk Chang ◽  
Sanghwan Lee
Keyword(s):  
Fuel Assembly ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Nuclear Fuel Assembly ◽  
Stress Analyses
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