Go to the main menu
Skip to content
Go to bottom
REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Nuclear Engineering and Technology
Journal Basic Information
Journal DOI :
Korean Nuclear Society
Editor in Chief :
Volume & Issues
Volume 39, Issue 6 - Dec 2007
Volume 39, Issue 5 - Oct 2007
Volume 39, Issue 4 - Aug 2007
Volume 39, Issue 3 - Jun 2007
Volume 39, Issue 2 - Apr 2007
Volume 39, Issue 1 - Feb 2007
Selecting the target year
THE IMPACT OF FUEL CYCLE OPTIONS ON THE SPACE REQUIREMENTS OF A HLW REPOSITORY
Kawata, Tomio ;
Nuclear Engineering and Technology, volume 39, issue 6, 2007, Pages 683~690
DOI : 10.5516/NET.2007.39.6.683
Because of increasing concerns regarding global warming and the longevity of oil and gas reserves, the importance of nuclear energy as a major source of sustainable energy is gaining recognition worldwide. To make nuclear energy truly sustainable, it is necessary to ensure not only the sustainability of the fuel supply but also the sustained availability of waste repositories, especially those for high-level radioactive waste (HLW). From this perspective, the effort to maximize the waste loading density in a given repository is important for easing repository capacity problems. In most cases, the loading of a repository is controlled by the decay heat of the emplaced waste. In this paper, a comparison of the decay heat characteristics of HLW is made among the various fuel cycle options. It is suggested that, for a future fast breeder reactor (FBR) cycle, the removal and burning of minor actinides (MA) would significantly reduce the heat load in waste and would allow for a reduction of repository size by half.
ASSESSING AND ADDRESSING INCREASED STAKEHOLDER AND OPERATOR INFORMATION NEEDS IN NUCLEAR FUEL CYCLE FACILITIES: TWO CONCEPTS
Saltiel, David H. ;
Nuclear Engineering and Technology, volume 39, issue 6, 2007, Pages 691~696
DOI : 10.5516/NET.2007.39.6.691
Nuclear energy programs around the world increasingly find themselves at the nexus of potentially conflicting demands from both domestic and international stakeholders. On one side, the rapid growth in demand for electricity coupled with the goal of reducing carbon emissions calls for a significant expansion of nuclear energy. On the other, stakeholders are seeking ever greater safety, environmental, security, and nonproliferation assurances before consenting to the construction of new nuclear energy facilities. Satisfying the demand for clean energy supplies will require nuclear energy operators to find new and innovative ways to build confidence among stakeholders. This paper discusses two related concepts which can contribute to meeting the needs of key stakeholders in cost effective and efficient ways. Structured processes and tools for assessing stakeholder needs can build trust and confidence while facilitating the "designing-in" of information collection systems for new facilities to achieve maximum efficiency and effectiveness. Integrated approaches to monitoring facilities and managing the resulting data can provide stakeholders with continued confidence while offering operators additional facility and process information to improve performance.
MOVING FORWARD WITH RADIOACTIVE WASTE MANAGEMENT IN THE UK
Atherton, Elizabeth ; Mathieson, John ;
Nuclear Engineering and Technology, volume 39, issue 6, 2007, Pages 697~702
DOI : 10.5516/NET.2007.39.6.697
Radioactive waste has been produced in the UK for many decades. Since the 1950' s much of this has been associated with civil nuclear power production and the nuclear weapons programme. There have been a number of unsuccessful attempts in the UK since the 1980s to deal with the waste and find suitable sites for its disposal. However, the UK Government has addressed this and in 2001 introduced the "Managing Radioactive Waste Safely" programme. The aim of this was to make decisions on the long-term radioactive waste management policy through stakeholder engagement. In 2006, it adopted a policy of geological disposal for higher activity wastes and following further consultations, is now at the stage of choosing how that policy should be implemented.
DEVELOPMENT OF AN INTEGRATED DECISION SUPPORT SYSTEM TO AID COGNITIVE ACTIVITIES OF OPERATORS
Lee, Seung-Jun ; Seong, Poong-Hyun ;
Nuclear Engineering and Technology, volume 39, issue 6, 2007, Pages 703~716
DOI : 10.5516/NET.2007.39.6.703
As digital and computer technologies have grown, human-machine interfaces (HMIs) have evolved. In safety-critical systems, especially in nuclear power plants (NPPs), HMIs are important for reducing operational costs, the number of necessary operators, and the probability of accident occurrence. Efforts have been made to improve main control room (MCR) interface design and to develop automated or decision support systems to ensure convenient operation and maintenance. In this paper, an integrated decision support system to aid operator cognitive processes is proposed for advanced MCRs of future NPPs. This work suggests the design concept of a decision support system which accounts for an operator's cognitive processes. The proposed system supports not only a particular task, but also the entire operation process based on a human cognitive process model. In this paper, the operator's operation processes are analyzed according to a human cognitive process model and appropriate support systems that support each cognitive process activity are suggested.
TIME-DOMAIN TECHNIQUE FOR FRONT-END NOISE SIMULATION IN NUCLEAR SPECTROSCOPY
Neamintara, Hudsaleark ; Mangclaviraj, Virul ; Punnachaiya, Suvit ;
Nuclear Engineering and Technology, volume 39, issue 6, 2007, Pages 717~724
DOI : 10.5516/NET.2007.39.6.717
A measurement-based time-domain noise simulation of radiation detector-preamplifier (front-end) noise in nuclear spectroscopy is described. The time-domain noise simulation was performed by generating "noise random numbers" using Monte Carlo's inverse method. The probability of unpredictable noise was derived from the empirical cumulative distribution function via the sampled noise, which was measured from a preamplifier output. Results of the simulated noise were investigated as functions of time, frequency, and statistical domains. Noise behavior was evaluated using the signal wave-shaping function, and was compared with the actual noise. Similarities between the response characteristics of the simulated and the actual preamplifier output noises were found. The simulated noise and the computed nuclear pulse signal were also combined to generate a simulated preamplifier output signal. Such simulated output signals could be used in nuclear spectroscopy to determine energy resolution degradation from front-end noise effect.
KERNEL-BASED NOISE FILTERING OF NEUTRON DETECTOR SIGNALS
Park, Moon-Ghu ; Shin, Ho-Cheol ; Lee, Eun-Ki ;
Nuclear Engineering and Technology, volume 39, issue 6, 2007, Pages 725~730
DOI : 10.5516/NET.2007.39.6.725
This paper describes recently developed techniques for effective filtering of neutron detector signal noise. In this paper, three kinds of noise filters are proposed and their performance is demonstrated for the estimation of reactivity. The tested filters are based on the unilateral kernel filter, unilateral kernel filter with adaptive bandwidth and bilateral filter to show their effectiveness in edge preservation. Filtering performance is compared with conventional low-pass and wavelet filters. The bilateral filter shows a remarkable improvement compared with unilateral kernel and wavelet filters. The effectiveness and simplicity of the unilateral kernel filter with adaptive bandwidth is also demonstrated by applying it to the reactivity measurement performed during reactor start-up physics tests.
A PRACTICAL METHOD FOR THE DISPOSAL OF RADIOACTIVE ORGANIC WASTE
Kim, Kil-Jeong ; Shon, Jong-Sik ; Ryu, Woo-Seog ;
Nuclear Engineering and Technology, volume 39, issue 6, 2007, Pages 731~736
DOI : 10.5516/NET.2007.39.6.731
Radioactive organic wastes containing acetone, alcohol, and particularly tributyl phosphate (TBP)/dodecane contaminated with uranium are extracted from the PUREX process and the decontamination of related equipment. An evaporation method that utilizes existing DU oxidation apparatuses and ventilation systems and a typical muffle furnace installed with an aspirating system are adopted. A separation method using phosphoric acid especially for the TBP/dodecane waste is also studied and evaluated. The results show that a simple evaporation process is utilizable for wastes containing acetone or alcohol with a lower boiling point. A modified muffle furnace is more appropriate to dispose directly of organic wastes having a higher boiling point, such as TBP/dodecane, without generating a condensed waste solution. It is recommended that, when the uranium concentration of TBP/dodecane waste is much higher than stipulated levels, separation technology should be applied to remove uranium from the mixture. Each type of solvent after separation can then be considered disposable below the regulatory limit in the modified furnace discussed in this study.
PERFORMANCE EVALUATION OF NEW SPACER GRID SHAPES FOR PWRS
Song, Kee-Nam ; Lee, Soo-Bum ; Lee, Sang-Hoon ;
Nuclear Engineering and Technology, volume 39, issue 6, 2007, Pages 737~746
DOI : 10.5516/NET.2007.39.6.737
A spacer grid, which is one of the most important structural components in a PWR fuel assembly, supports its fuel rods laterally and vertically. Based on in-house design experience, scrutiny of the design features of advanced nuclear fuels and the patents of other spacer grids, KAERI has devised its own spacer grid shapes and acquired patents. In this study, a performance evaluation of KAERI's spacer grid shapes was carried out from mechanical/structural and thermohydraulic view points. A comparative performance evaluation of commercial spacer grid shapes was also carried out. The comparisons addressed the spring characteristics, fuel rod vibration characteristics, fretting wear resistance, impact strength characteristics, CHF enhancement, and the pressure drop level of the spacer grid shapes. The results show that the performances of KAERI's spacer grid shapes are as good as or better than those of the commercial spacer grid shapes.
INITIAL ESTIMATION OF THE RADIONUCLIDES IN THE SOIL AROUND THE 100 MEV PROTON ACCELERATOR FACILITY OF PEFP
An, So-Hyun ; Lee, Young-Ouk ; Cho, Young-Sik ; Lee, Cheol-Woo ;
Nuclear Engineering and Technology, volume 39, issue 6, 2007, Pages 747~752
DOI : 10.5516/NET.2007.39.6.747
The Proton Engineering Frontier Project (PEFP) has designed and developed a proton linear accelerator facility operating at 100 MeV - 20 mA. The radiological effects of such a nuclear facility on the environment are important in terms of radiation safety. This study estimated the production rates of radionuclides in the soil around the accelerator facility using MCNPX. The groundwater migration of the radioisotopes was also calculated using the Concentration Model. Several spallation reactions have occurred due to leaked neutrons, leading to the release of various radionuclides into the soil. The total activity of the induced radionuclides is approximately
at the point of saturation.
had the highest production rate with a specific activity of
over the course of one year.
are usually considered the most important radioisotopes at nuclear facilities. However, only a small amount of tritium was produced around this facility, as the energy of most neutrons is below the threshold of the predominant reactions for producing tritium:
(approximately 20 MeV). The dose level of drinking water from
pCi/ml/yr, which was less than the annual intake limit in the regulations.