• Title/Summary/Keyword: Reprocessing

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A study on the Measurement of the Coefficient of Thermal Expansion of Polymer materials Exposed to Different Thermal Environments (서로 다른 열환경에 노출된 고분자 소재의 열팽창계수 측정에 관한 연구)

  • Kim, Dong-Ju;Park, Seul-Hyun
    • Journal of the Korean Society of Manufacturing Process Engineers
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    • v.20 no.4
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    • pp.80-86
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    • 2021
  • Plastics are widely used in mechanical and other fields due to their light weight, design flexibility, and molding processability. In processing plastics, defective products are mixed and reprocessed to improve production efficiency and reduce costs. In this study, an experiment was conducted to confirm the coefficient of thermal expansion of HDPE during this reprocessing. The coefficient of thermal expansion was measured at different measurement directions and heating rates. As a result, we observed that the coefficient of thermal expansion in the direction perpendicular to the injection direction is greater than that in the horizontal direction.

Thermal stability of nitric acid solutions of reducing agents used in spent nuclear fuel reprocessing

  • Obedkov, A.S.;Kalistratova, V.V.;Skvortsov, I.V.;Belova, E.V.
    • Nuclear Engineering and Technology
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    • v.54 no.9
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    • pp.3580-3585
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    • 2022
  • The thermal stability of carbohydrazide, hydrazine nitrate, acetohydroxamic acid in nitric acid solutions has been studied at atmospheric pressure and above atmospheric pressure. The volumes of gaseous products of thermolysis and the maximum rate of gas evolution have been determined at atmospheric pressure. It has been shown that, despite the high rate of gas evolution and large volumes of evolved gases, the conditions for the development of autocatalytic oxidation are not created. Exothermic processes are observed in a closed vessel in the temperature range of 50-250 ℃. With an increase in the concentration of nitric acid, the temperatures of the onset of exothermic effects for all mixtures decrease, and the values of the total thermal effects of reactions increase, to the greatest extent for solutions with carbohydrazide.

A Concise Review of High Performance PPS Composites using Various Fillers

  • Ahn, Seonghyeon;Park, Chanil;Choi, Jae-Hak;Kim, Yong Seok;Yoo, Youngjae
    • Elastomers and Composites
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    • v.57 no.3
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    • pp.81-91
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    • 2022
  • Composites based on engineering thermoplastics exhibit excellent mechanical and thermal properties and simple processing and reprocessing attributes, and are widely used in the aerospace, three-dimensional (3D) printing, and automobile industries. Polyphenylene sulfide (PPS) is one of the most desirable engineering thermoplastics, owing to its superior thermal performance, inherent flame retardancy resulting from the presence of sulfur in its backbone structure, chemical resistance, and satisfactory electrical properties. However, pure PPS resin has limited applicability owing to its brittleness. To compensate for these shortcomings, various filler materials are frequently used in the manufacture of PPS composites. In this review, we would like to present the correlation between the structure and physical properties of PPS composite materials using various fillers.

Plutonium mass estimation utilizing the (𝛼,n) signature in mixed electrochemical samples

  • Gilliam, Stephen N.;Coble, Jamie B.;Goddard, Braden
    • Nuclear Engineering and Technology
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    • v.54 no.6
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    • pp.2004-2010
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    • 2022
  • Quantification of sensitive material is of vital importance when it comes to the movement of nuclear fuel throughout its life cycle. Within the electrorefiner vessel of electrochemical separation facilities, the task of quantifying plutonium by neutron analysis is especially challenging due to it being in a constant mixture with curium. It is for this reason that current neutron multiplicity methods would prove ineffective as a safeguards measure. An alternative means of plutonium verification is investigated that utilizes the (𝛼,n) signature that comes as a result of the eutectic salt within the electrorefiner. This is done by utilizing the multiplicity variable a and breaking it down into its constituent components: spontaneous fission neutrons and (𝛼,n) yield. From there, the (𝛼,n) signature is related to the plutonium content of the fuel.

Sterilizing Effect of Plant Pathogenic Fungi using Ozone Microbubble (오존마이크로버블을 이용한 식물병원균 살균효과)

  • Kim, Chang Shoo;Yu, Sang Yeol;Lee, Gong In;Kim, Seung Han;Lee, Jong Won;Song, Jae Kwan
    • Journal of Bio-Environment Control
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    • v.23 no.3
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    • pp.250-255
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    • 2014
  • Sterilization is an important factor in reprocessing of drained nutrient solution (RDN). To evaluate the suitability of ozone microbubble for RDN in protected horticulture and plant factory, strong fungicidal activity of ozone and microbubble were applied. This experiment was taken advantage of ozonated water (OW) and ozone gas (OG). The Fusarium oxysporum (FO), Phytophthora capsici (PC) and Colletotrichum gloeosporioides (CG) were treated with OW 0.5, 1.0 and 2.0 ppm and OG $3.0g{\cdot}h^{-1}$ for 0, 30, 60, 120 and 180 sec. Results of this experiment can be summed up as follows : In the OW, FO was sterilized by 0.5 ppm in 60 sec and PC was sterilized by 2.0 ppm in 30 sec. In the OG, FO and PC both of them were sterilized in 180 sec. However, CG was not sterilized using OW and OG. Overall, ozone microbubble showed possibility of sterilization in RDN. However, CG is required to more ozone concentration and processing time.

TERRAPOWER, LLC TRAVELING WAVE REACTOR DEVELOPMENT PROGRAM OVERVIEW

  • Hejzlar, Pavel;Petroski, Robert;Cheatham, Jesse;Touran, Nick;Cohen, Michael;Truong, Bao;Latta, Ryan;Werner, Mark;Burke, Tom;Tandy, Jay;Garrett, Mike;Johnson, Brian;Ellis, Tyler;Mcwhirter, Jon;Odedra, Ash;Schweiger, Pat;Adkisson, Doug;Gilleland, John
    • Nuclear Engineering and Technology
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    • v.45 no.6
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    • pp.731-744
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    • 2013
  • Energy security is a topic of high importance to many countries throughout the world. Countries with access to vast energy supplies enjoy all of the economic and political benefits that come with controlling a highly sought after commodity. Given the desire to diversify away from fossil fuels due to rising environmental and economic concerns, there are limited technology options available for baseload electricity generation. Further complicating this issue is the desire for energy sources to be sustainable and globally scalable in addition to being economic and environmentally benign. Nuclear energy in its current form meets many but not all of these attributes. In order to address these limitations, TerraPower, LLC has developed the Traveling Wave Reactor (TWR) which is a near-term deployable and truly sustainable energy solution that is globally scalable for the indefinite future. The fast neutron spectrum allows up to a ~30-fold gain in fuel utilization efficiency when compared to conventional light water reactors utilizing enriched fuel. When compared to other fast reactors, TWRs represent the lowest cost alternative to enjoy the energy security benefits of an advanced nuclear fuel cycle without the associated proliferation concerns of chemical reprocessing. On a country level, this represents a significant savings in the energy generation infrastructure for several reasons 1) no reprocessing plants need to be built, 2) a reduced number of enrichment plants need to be built, 3) reduced waste production results in a lower repository capacity requirement and reduced waste transportation costs and 4) less uranium ore needs to be mined or purchased since natural or depleted uranium can be used directly as fuel. With advanced technological development and added cost, TWRs are also capable of reusing both their own used fuel and used fuel from LWRs, thereby eliminating the need for enrichment in the longer term and reducing the overall societal waste burden. This paper describes the origins and current status of the TWR development program at TerraPower, LLC. Some of the areas covered include the key TWR design challenges and brief descriptions of TWR-Prototype (TWR-P) reactor. Selected information on the TWR-P core designs are also provided in the areas of neutronic, thermal hydraulic and fuel performance. The TWR-P plant design is also described in such areas as; system design descriptions, mechanical design, and safety performance.

A Study on the Radio-activity Reduction Method for the Decladding Hull

  • Kim, Jong-Ho;Jung, In-Ha;Park, Jang-Jin;Shin, Jin-Myeong;Lee, Ho-Hee;Yang, Myung-Seung
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.02a
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    • pp.130-139
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    • 2004
  • The cladding materials remaining after reprocessing process of the nuclear fuel, generally called as hulls, are classified as a high-level radioactive waste. They are usually packaged in the container for disposal after being compacted, melted, or solidified into the matrix. The efforts to fabricate a better ingot for a more favorable disposal to the environment have failed due to the technical difficulties encountered in the chemical decontamination method. In the early 1990s, the accumulation of radio-chemical data on hulls and the advent of new technology such as a laser or plasma have made the pre-treatment of the hulls more efficient. This paper summarizes the information regarding the radio-chemical analysis of the hull through a literature survey and determines the characteristics of the hull and depth profile of the radio-nuclides within the hull thickness. The feasibility study was carried out to evaluate the reduction of the radioactivity by peeling off the surface of the hull with the application of laser technology.

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Fuel Cycle Strategy of Go-ri Nuclear Power Plant - A Statistical Analysis -

  • Chung, Chang-Hyun;Kim, Chang-Hyo
    • Nuclear Engineering and Technology
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    • v.9 no.3
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    • pp.139-149
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    • 1977
  • An attempt is made to establish an optimum fuel cycle strategy for the Go-ri nuclear power plant units 1 and 2. The total capital required for the fuel cycle operation is selected as a figure of merit for economic comparison of several alternative fuel cycle schemes available for the plant, and evaluated using a probabilistic method coupled with a sampling procedure of the fluctuating fuel cost data. The results are presented in the form of probability histograms. On the basis of the most likely values of the capital requirement obtained from the histograms, a conclusion is drawn that reprocessing cycle with either uranium only or both uranium and plutonium recycled is the most economic choice for the Go-ri plant.

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A Case Study on the Planning Characteristic and It's Application of Container Architecture in Europe (유럽 컨테이너 건축물의 사례분석을 통한 국내 적용방안)

  • Kim, Mi-Kyoung;Mun, Young-A;Han, Su-Ji
    • Journal of the Korean housing association
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    • v.26 no.1
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    • pp.43-51
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    • 2015
  • The purpose of this study was to analyze the planning characteristics and it's application of container architecture as case study. Field survey was used to analyze the spatial planning characteristics in terms of development outline, appearance, exterior, floor plan and interior of eight famous cases in Berlin, Hamburg, Hannover, Amsterdam and Paris of Europe. The results of this study were as follows; Firstly, good examples of container architectures such as student housing, social service center, temporary medical facility and cruise terminal in Europe suggested the potential of domestic applicability in various purposes and development. Secondly, various types of freight container, building container and module frame system should be developed with their reprocessing environment. Thirdly, it is necessary for us to develop ISO type(20~40ft) container and standard plan with interior and storage design reflecting demands of residents. Finally, the use of container module will be an environmental-friendly alternative for its modularity and reusability, so it should be used as it is without severe deformation. The development of environmental friendly energy sources such as hydro and solar power is necessary for domestic container architecture as well. The container design should include the use of high quality of exterior finishing materials and the plan of aesthetical color planning to make the building a local landmark.

Chemical Treatment of Low-level Radioactive Liquid Waste (I)

  • Lee, Sang-Hoon;Choe, Jong-In;Kim, Yong-Eak
    • Nuclear Engineering and Technology
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    • v.8 no.2
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    • pp.69-76
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    • 1976
  • This experiment has been carried out for the removal of long-lived radioactive-nuclides (Sr-90, Ru-106, Cs-137 and Ce-144) contained in the low-level radioactive effluents from the spent fuel reprocessing plant and nuclear power plant, in order to determine the decontaminability of various chemical coagulants and domestic clay mineral (montmorillonite). Phosphate process showed prominent efficiency for the removal of Ce-144, and lime-soda process did good removal efficiency for Sr-90. About Cs-137 copper-ferrocyanide process is much desirable. In phosphate or lime-soda process, most favorable removal efficiency was obtained at more than pH 11. The montmorillonite treated with sodium chloride showed a considerable improvement in the removal of the radioactive-nuclides. By a combined chemicals-montmorillionite process, the radioactive-nuclides could be more effectively removed than by the only chemicals process.

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