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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
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Nuclear Engineering and Technology
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Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 43, Issue 6 - Dec 2011
Volume 43, Issue 5 - Oct 2011
Volume 43, Issue 4 - Aug 2011
Volume 43, Issue 3 - Jun 2011
Volume 43, Issue 2 - Apr 2011
Volume 43, Issue 1 - Feb 2011
Selecting the target year
PYROPROCESSING TECHNOLOGY DEVELOPMENT AT KAERI
Lee, Han-Soo ; Park, Geun-Il ; Kang, Kweon-Ho ; Hur, Jin-Mok ; Kim, Jeong-Guk ; Ahn, Do-Hee ; Cho, Yung-Zun ; Kim, Eung-Ho ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 317~328
DOI : 10.5516/NET.2011.43.4.317
Pyroprocessing technology was developed in the beginning for metal fuel treatment in the US in the 1960s. The conventional aqueous process, such as PUREX, is not appropriate for treating metal fuel. Pyroprocessing technology has advantages over the aqueous process: less proliferation risk, treatment of spent fuel with relatively high heat and radioactivity, compact equipment, etc. The addition of an oxide reduction process to the pyroprocessing metal fuel treatment enables handling of oxide spent fuel, which draws a potential option for the management of spent fuel from the PWR. In this context, KAERI has been developing pyroprocessing technology to handle the oxide spent fuel since the 1990s. This paper describes the current status of pyroprocessing technology development at KAERI from the head-end process to the waste treatment. A unit process with various scales has been tested to produce the design data associated with the scale up. A performance test of unit processes integration will be conducted at the PRIDE facility, which will be constructed by early 2012. The PRIDE facility incorporates the unit processes all together in a cell with an Ar environment. The purpose of PRIDE is to test the processes for unit process performance, operability by remote equipment, the integrity of the unit processes, process monitoring, Ar environment system operation, and safeguards related activities. The test of PRIDE will be promising for further pyroprocessing technology development.
PYROPROCESSING FLOWSHEETS FOR RECYCLING USED NUCLEAR FUEL
Williamson, M.A. ; Willit, J.L. ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 329~334
DOI : 10.5516/NET.2011.43.4.329
Two conceptual flowsheets were developed for recycling used nuclear fuel. One flowsheet was developed for recycling used oxide nuclear fuel from light water reactors while the other was developed for recycling used metal fuel from fast spectrum reactors. Both flowsheets were developed from a set of design principles including efficient actinide recovery, nonproliferation, waste minimization and commercial viability. Process chemistry is discussed for each unit operation in the flowsheet.
ELECTROCHEMICAL PROCESSING OF USED NUCLEAR FUEL
Goff, K.M. ; Wass, J.C. ; Marsden, K.C. ; Teske, G.M. ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 335~342
DOI : 10.5516/NET.2011.43.4.335
As part of the Department of Energy's Fuel Cycle Research and Development Program an electrochemical technology employing molten salts is being developed for recycle of metallic fast reactor fuel and treatment of light water reactor oxide fuel to produce a feed for fast reactors. This technology has been deployed for treatment of used fuel from the Experimental Breeder Reactor II (EBR-II) in the Fuel Conditioning Facility, located at the Materials and Fuel Complex of Idaho National Laboratory. This process is based on dry (non-aqueous) technologies that have been developed and demonstrated since the 1960s. These technologies offer potential advantages compared to traditional aqueous separations including: compactness, resistance to radiation effects, criticality control benefits, compatibility with advanced fuel types, and ability to produce low purity products. This paper will summarize the status of electrochemical development and demonstration activities with used nuclear fuel, including preparation of associated high-level waste forms.
MASS ESTIMATION OF IMPACTING OBJECTS AGAINST A STRUCTURE USING AN ARTIFICIAL NEURAL NETWORK WITHOUT CONSIDERATION OF BACKGROUND NOISE
Shin, Sung-Hwan ; Park, Jin-Ho ; Yoon, Doo-Byung ; Choi, Young-Chul ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 343~354
DOI : 10.5516/NET.2011.43.4.343
It is critically important to identify unexpected loose parts in a nuclear reactor pressure vessel, since they may collide with and cause damage to internal structures. Mass estimation can provide key information regarding the kind as well as the location of loose parts. This study proposes a mass estimation method based on an artificial neural network (ANN), which can overcome several unresolved issues involved in other conventional methods. In the ANN model, input parameters are the discrete cosine transform (DCT) coefficients of the auto-power spectrum density (APSD) of the measured impact acceleration signal. The performance of the proposed method is then evaluated through application to a large-sized plate and a 1/8-scaled mockup of a reactor pressure vessel. The results are compared with those obtained using a conventional method, the frequency ratio (FR) method. It is shown that the proposed method is capable of estimating the impact mass with 30% lower relative error than the FR method, thus improving the estimation performance.
A TEST VERIFIED MODEL DEVELOPMENT STUDY FOR A NUCLEAR WATER CHILLER USING THE SEISMIC QUALIFICATION ANALYSIS AND TEST
Sur, Uk-Hwan ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 355~360
DOI : 10.5516/NET.2011.43.4.355
This paper is a study on a nuclear water chiller. It presents a test-verified finite element model of a water chiller to be used at a Nuclear Power Plant. The test-verified model predicts natural frequencies within 5% for all major modes below 50 Hz. This model accurately represents the dynamic characteristics of the actual hardware and is qualified for its use in the final stress analysis for seismic verification.
MATHEMATICAL ANALYSIS USING TWO MODELING TECHNIQUES FOR DYNAMIC RESPONSES OF A STRUCTURE SUBJECTED TO A GROUND ACCELERATION TIME HISTORY
Kim, Yong-Woo ; Jhung, Myung-Jo ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 361~374
DOI : 10.5516/NET.2011.43.4.361
Two types of numerical modeling techniques were considered for the dynamic response of a structure subjected to a ground acceleration. One technique is based on the equation of motion relative to ground motion, and the other is based on the equation of absolute motion of the structure and the ground. The analytic background of the former is well established while the latter has not yet been extensively verified. The latter is called a large mass method, which allocates an appropriate large mass to the ground so that it causes the ground to move according to a given acceleration time history. In this paper, through the use of a single degree-of-freedom spring-mass system, the equations of motion of the two techniques were analyzed and useful theorems are provided on the large mass method. Using simple examples, the numerical results of the two modeling techniques were compared with analytic solutions. It is shown that the theorems provide a clear insight on the large mass method.
NUCLEAR HUMAN RESOURCE PROJECTION UP TO 2030 IN KOREA
Min, Byung-Joo ; Lee, Man-Ki ; Nam, Kee-Yung ; Jeong, Ki-Ho ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 375~382
DOI : 10.5516/NET.2011.43.4.375
The prospects for growth of the nuclear power industry in Korea have improved remarkably as the demand for energy increases in stride with economic development. Meanwhile, as nuclear energy development is enhanced, nuclear technology has also improved evolutionarily and innovatively in the areas of reactor design and safety measures. As nuclear technology development in Korea advances, more human resources are required. Accordingly, the need for a well-managed program of human resource development (HRD) aimed at assuring needed capacities, skills, and knowledge and maintaining valuable human resources through education and training in various nuclear-related fields has been recognized. A well-defined and object-oriented human resource development and management (HRD&M) is to be developed in order to balance between the dynamics of supply and demand of the workforce in the nuclear industry. The HRD&M schemes include a broad base of disciplines, education, sciences, and technologies within a framework of national sustainable development goals, which are generally considered to include economics, environment, and social concerns. In this study, the projection methodology considering a variety of economic, social, and environmental factors was developed. Using the developed methodology, medium- and long-term nuclear human resources projections up to 2030 were conducted in compliance with the national nuclear technology development programmes and plans.
LINEAR PROGRAMMING OPTIMIZATION OF NUCLEAR ENERGY STRATEGY WITH SODIUM-COOLED FAST REACTORS
Lee, Je-Whan ; Jeong, Yong-Hoon ; Chang, Yoon-Il ; Chang, Soon-Heung ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 383~390
DOI : 10.5516/NET.2011.43.4.383
Nuclear power has become an essential part of electricity generation to meet the continuous growth of electricity demand. A Sodium-cooled Fast Reactor (SFR) was developed to extend uranium resource utilization under a growing nuclear energy scenario while concomitantly providing a nuclear waste management solution. Key questions in this scenario are when to introduce SFRs and how many reactors should be introduced. In this study, a methodology using Linear Programming is employed in order to quantify an optimized growth pattern of a nuclear energy system comprising light water reactors and SFRs. The optimization involves tradeoffs between SFR capital cost premiums and the total system U3O8 price premiums. Optimum nuclear growth patterns for several scenarios are presented, as well as sensitivity analyses of important input parameters.
A STUDY ON OXIDATION TREATMENT OF URANIUM METAL CHIP UNDER CONTROLLING ATMOSPHERE FOR SAFE STORAGE
Kim, Chang-Kyu ; Ji, Chul-Goo ; Bae, Sang-Oh ; Woo, Yoon-Myeoung ; Kim, Jong-Goo ; Ha, Yeong-Keong ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 391~398
DOI : 10.5516/NET.2011.43.4.391
The U metal chips generated in developing nuclear fuel and a gamma radioisotope shield have been stored under immersion of water in KAERI. When the water of the storing vessels vaporizes or drains due to unexpected leaking, the U metal chips are able to open to air. A new oxidation treatment process was raised for a long time safe storage with concepts of drying under vacuum, evaporating the containing water and organic material with elevating temperature, and oxidizing the uranium metal chips at an appropriate high temperature under conditions of controlling the feeding rate of oxygen gas. In order to optimize the oxidation process the uranium metal chips were completely dried at higher temperature than
and tested for oxidation at various temperatures, which are
. When the oxidation temperature was
, the oxidized sample for 7 hours showed a temperature rise of
in the self-ignition test. But the oxidized sample for 14 hours revealed a slight temperature rise of
representing a stable behavior in the self-ignition test. When the temperature was
, the shorter oxidation for 7 hours appeared to be enough because the self-ignition test represented no temperature rise. By using several chemical analyses such as carbon content determination, X-ray deflection (XRD), Infrared spectra (IR) and Thermal gravimetric analysis (TGA) on the oxidation treated samples, the results of self-ignition test of new oxidation treatment process for U metal chip were interpreted and supported.
DEVELOPMENT AND EVALUATION OF A PHANTOM FOR MULTI-PURPOSE DOSIMETRY IN INTENSITY-MODULATED RADIATION THERAPY
Jeong, Hae-Sun ; Han, Young-Yih ; Kum, O-Yeon ; Kim, Chan-Hyeong ; Park, Joo-Hwan ;
Nuclear Engineering and Technology, volume 43, issue 4, 2011, Pages 399~404
DOI : 10.5516/NET.2011.43.4.399
A LEGO-type multi-purpose dosimetry phantom was developed for intensity-modulated radiation therapy (IMRT), which requires various types of challenging dosimetry. Polystyrene, polyethylene, polytetrafluoroethylene (PTFE), and polyurethane foam (PU-F) were selected to represent muscle, fat, bone, and lung tissue, respectively, after considering the relevant mass densities, elemental compositions, effective atomic numbers, and photon interaction coefficients. The phantom, which is composed of numerous small pieces that are similar to LEGO blocks, provides dose and dose distribution measurements in homogeneous and heterogeneous media. The phantom includes dosimeter holders for several types of dosimeters that are frequently used in IMRT dosimetry. An ion chamber and a diode detector were used to test dosimetry in heterogeneous media under radiation fields of various sizes. The data that were measured using these dosimeters were in disagreement when the field sizes were smaller than
for polystyrene and PTFE, or smaller than
for an air cavity. The discrepancy was as large as 41% for the air cavity when the field size was
, highlighting one of the challenges of IMRT small field dosimetry. The LEGO-type phantom is also very useful for two-dimensional dosimetry analysis, which elucidates the electronic dis-equilibrium phenomena on or near the heterogeneity boundaries.