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Cost Comparison of PWR and PHWR Nuclear Power Plants in Korea

  • Kim, Chang-Hyo;Chung, Chang-Hyun;So, Dong-Sub
    • Nuclear Engineering and Technology
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    • v.11 no.4
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    • pp.263-274
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    • 1979
  • A statistical approach is used to investigate the relative economic advantages of pressurized water reactor (PWR) and pressurized heavy water reactor (PHWR-CANDU) nuclear power plants for hypothetical 900Mwe systems with the throwaway fuel cycle to be built in the Republic of Korea. Power cost is decomposed into the cost components related to the plant capital, operation and maintenance, working capital requirements and fuel cycle operation. The calculation of construction cost is performed with the modified version of computer code ORCOST, and the modified POWERCO-50 is used to evaluate the cost components. Most of economic parameters are treated as statistical variables, each being given with a certain range. Through a random sampling procedures. the probability histograms on unit plant construction costs and power generating costs are obtained. The power cost probability histograms of the PWR and the PHWR plants overlap considerably, and the power costs of two systems appear to be almost same with the PHWR power cost being 0.4mil1/kwh lower compared with 39.4 mills/kwh for the PWR plant (July 1986 US-dollars). When a construction period of PHWR plant is longer by one year than that of PWR plant, there is no difference in the unit power cost of two plants. This comparison leads to no definite conclusion on the cost advantage of the PWR plant versus the PHWR plant. We conclude that the selection issue of nuclear power plants in Korea still remains an open question and that future effort to solve this question should be made toward economic quantification of those factors such as technology transfer and localization.

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International Study and Transformational Learning: What Covid-19 Has Taught Us

  • Rodgers, Steve
    • International conference on construction engineering and project management
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    • 2022.06a
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    • pp.1221-1221
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    • 2022
  • Studying abroad in and of itself should be a unique and transformational learning experience for university students. Too often, "study abroad" is a code word for "faculty vacation" or "easy credit hours". For an international learning experience to be truly transformational it must offer an intense and directed program that maximizes the time the student spends in the accumulation of information that is new or different from what the student has "learned" previously. "Study abroad" may be a misnomer because it is not only about studying in another country or culture, that is, taking courses that usually have an attendance time of a few hours a week, but it is also about living in another country which becomes a 24/7 learning experience. Providing these programs during the Covid-19 pandemic has been a keen opportunity for institutional learning. When this immersion in foreign culture is combined with academic rigor applied to a student's chosen field of study the growth can be exponential. So, what is the relationship between academic and personal growth? The National Association for Study Abroad has found that "students who have studied abroad are better able to work with people from other countries, understand the complexity of global issues, and have greater intercultural learning. One study found that students returned from their study abroad experiences more tolerant and less fearful of other countries, but with a greater sense of nationalism-a phenomenon they called 'enlightened nationalism'." It is often said that "you only really learn to appreciate things that are important to you when they are gone, when you miss them." The international learning environment can provide this opportunity. The restrictions on various societies in the past two years due to the international Covid pandemic have provided existing study abroad programs with a true testing ground for the validity of their programs. At the end of the day, American colleges and universities are not helpless in the face of these developments. A lot depends on how a university positions itself for a future based on the uncertainties of the past. As Winston Churchill was working to form the United Nations after WWII, he famously said, "Never let a good crisis go to waste". In another context, Churchill's insight on human nature can also be applied to the coming semesters and years as studying abroad rebounds. What new strategies will be developed and maintained? Institutional commitment without fear will be necessary to assure that "studying abroad" will continue to develop as a truly unique and transformational learning experience.

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Applications of Korean National Traffic DB in TRANSIMS (TRANSIMS에서 국가교통DB의 적용방안)

  • Kwon, Kee-Wook;Lee, Jong-Dal
    • Journal of the Korean Association of Geographic Information Studies
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    • v.13 no.2
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    • pp.29-40
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    • 2010
  • Car simulation by TRANSIMS is able to rapidly analyze the broad area based on CA(Cellular Automata) theory, which is the great advantage compared to other existing programs. As the source code of TRANSIMS is open, it may be modified by incorporating the network and traffic characteristics. This study uses the traffic thematic map built in the Korean National Traffic DB(KTDB) center among input date used for building network data of TRANSIMS. However, because the traffic thematic map is not composed as the type required by TRANSIMS, it was corrected and complemented to build a network, and the traffic volume at arterial roads and the traffic volume at each direction of the intersection was calculated through simulation for the area of Suseong-Gu, Daegu Metro. This was compared to the actual traffic volume. As a result of the simulation, it shows error from 14% to 42% at intersection, and from 3% to 8% at arterial roads. This result is very satisfactory because the entire traffic volume of Daegu Metro was not considered, and the tendency of drivers avoiding path due to construction on certain section, the status of road surface and chronic congestion was not reflected.

Development of a Computation Code for the Verification of the Vulnerability Criteria for Surf-riding and Broaching Mode of IMO Second-Generation Intact Stability Criteria (IMO 2세대 선박 복원성 기준에 따른 서프라이딩/ 브로칭 취약성 기준 검증을 위한 계산 코드 개발)

  • Shin, Dong Min;Oh, Kyoung-gun;Moon, Byung Young
    • Journal of Ocean Engineering and Technology
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    • v.33 no.6
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    • pp.518-525
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    • 2019
  • Recently, the Sub-Committee on SDC (Ship Design and Construction) of IMO have discussed actively the technical issues associated with the second-generation intact stability criteria of ships. Generally, second generation intact stability criteria refer to vulnerability five modes ship stability which occurs when the ship navigating in rough seas. As waves passes the ship, dynamic roll motion phenomenon will affect ship stability that may lead to capsizing. Multi-tiered approach for second generation of intact stability criteria of IMO instruments covers apply for all ships. Each ship is checked for vulnerability to pure loss of stability, parametric roll, and broaching/surf-riding phenomena using L1(level 1) vulnerability criteria. If a possible vulnerability is detected, then the L2(level 2) criteria is used, followed by direct stability assessment, if necessary. In this study, we propose a new method to verify the criteria of the surf-riding/broaching mode of small ships. In case, L1 vulnerability criteria is not satisfied based on the relatively simple calculation using the Froude number, we presented the calculation code for the L2 criteria considering the hydrodynamics in waves to perform the more complicated calculation. Then the vulnerability criteria were reviewed based on the data for a given ship. The value of C, which is the probability of the vulnerability criteria for surf-riding/broaching, was calculated. The criteria value C is considered in new approach method using the Froude-Krylov force and the diffraction force. The result shows lower values when considering both the Froude-rylov force and the diffraction force than with only the Froude-Krylov force was considered. This difference means that when dynamic roll motion of ship, more exact wave force needs considered for second generation intact stability criteria This result will contribute to basic ship design process according to the IMO Second-Generation Intact Stability Criteria.

Development and Evaluation of Hollow-head Precast Reinforced Concrete Pile (말뚝머리 중공 프리캐스트 철근콘크리트 말뚝의 성능 평가)

  • Bang, Jin-Wook;Hyun, Jung-Hwan;Ahn, Kyung-Chul;Kim, Yun-Yong
    • Journal of the Korea institute for structural maintenance and inspection
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    • v.21 no.2
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    • pp.130-137
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    • 2017
  • Due to the economic growth and development of construction technology, a role of foundation to resist heavy loads has been increased. In this present study to improve the structural performance of reinforced concrete pile, the precast HPC pile reinforced with rebar and filling concrete was developed and the strength of pile was predicted based on the limit state design method. The safety of HPC pile strength was evaluated by comparing with the design values. The geometry of HPC pile is a decagon cross section with a maximum width of 500 mm and a minimum width of 475 mm, and the hollow head of pile thickness is 70 mm. The inner area of the hollow head part was made as the square ribbed shape presented in the limit state design code in order to achieve horizontal shear strength between pile concrete and filling concrete. From the shear test results, it was found that the stable shear strength were secured without abrupt failure until maximum load stage despite the shear cracks was found. Shear strength is 135% and 119% higher than that of design value calculated from limit state design code. The driving test results of HPC pile according to the presence of additional reinforcement showed the outstanding crack resistance against impact loads condition. From the bending test results the flexural load between PHC pile and HPC pile was 1.51 times and 1.48 times higher than that of the design flexural load of conventional PHC pile.

Behavior of 550MPa 43mm Hooked Bars Embedded in Beam-Column Joints (보-기둥 접합부에 정착된 550 MPa 43 mm 갈고리철근의 거동)

  • Bae, Min-Seo;Chun, Sung-chul;Kim, Mun-Gil
    • Journal of the Korea Concrete Institute
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    • v.28 no.5
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    • pp.611-620
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    • 2016
  • In the construction of nuclear power plants, only 420 MPa reinforcing bars are allowed and, therefore, so many large-diameter bars are placed, which results in steel congestion. Consequently, re-bar works are difficult and the quality of RC structures may be deteriorated. To solve the steel congestion, 550 MPa bars are necessary. Among many items for verifying structural performance of reinforced concrete with 550 MPa bars, the 43 mm hooked bars are examined in this study. All specimens failed by side-face blowout and the side cover explosively spalled at maximum loads. The bar force was initially transferred to the concrete primarily by bond along a straight portion. At the one third of maximum load, the bond reached a peak capacity and began to decline, while the hook bearing component rose rapidly. At failure, most load was resisted by the hook bearing. For confined specimens with hoops, the average value of test-to-prediction ratios by KCI code is 1.45. The modification factor of confining reinforcement which was not allowed for larger than 35 mm bars can be applied to 43 mm hooked bars. For specimens with 70 MPa concrete, the average value of test-to-prediction ratios by KCI code is 1.0 which is less than the values of the other specimens. The effects of concrete compressive strength should be reduced. An equation to predict anchorage capacity of hooked bars was developed from regression analysis including the effects of compressive strength of concrete, embedment length, side cover thickness, and transverse reinforcement index.

Development of a Short-term Failure Assessment of High Density Polyethylene Pipe Welds - Application of the Limit Load Analysis - (고밀도 폴리에틸렌 융착부에 대한 단기간 파손 평가법 개발 - 한계하중 적용 -)

  • Ryu, Ho-Wan;Han, Jae-Jun;Kim, Yun-Jae;Kim, Jong-Sung;Kim, Jeong-Hyeon;Jang, Chang-Heui
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.39 no.4
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    • pp.405-413
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    • 2015
  • In the US, the number of cases of subterranean water contamination from tritium leaking through a damaged buried nuclear power plant pipe continues to increase, and the degradation of the buried metal piping is emerging as a major issue. A pipe blocked from corrosion and/or degradation can lead to loss of cooling capacity in safety-related piping resulting in critical issues related to the safety and integrity of nuclear power plant operation. The ASME Boiler and Pressure Vessel Codes Committee (BPVC) has recently approved Code Case N-755 that describes the requirements for the use of polyethylene (PE) pipe for the construction of Section III, Division 1 Class 3 buried piping systems for service water applications in nuclear power plants. This paper contains tensile and slow crack growth (SCG) test results for high-density polyethylene (HDPE) pipe welds under the environmental conditions of a nuclear power plant. Based on these tests, the fracture surface of the PENT specimen was analyzed, and the fracture mechanisms of each fracture area were determined. Finally, by using 3D finite element analysis, limit loads of HDPE related to premature failure were verified.

Tensile Test for Lap Welded Joints of Rebars(SD400) (일반철근(SD400) 용접 겹침이음 인장실험)

  • Park, Won-Tae;Chun, Kyoung-Sik
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.19 no.5
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    • pp.570-576
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    • 2018
  • In reinforced concrete structures, the joints of ordinary rebars are usually lap joints, which are bound by binding wires with rebars, and mechanical joints by couplers. In domestic design standards (concrete design code), welded lap joints are restricted for ordinary rebars, but overseas standards allow welded lap joints of ordinary rebars through pre-heating. This study investigated the domestic and international standards/criteria and evaluated the fracture strength by performing the tensile test on the lap welded joint of SD400 grade rebars, which is used the most in the construction sites. The weld length of the specimen for weld lap joints is based on the minimum weld length (8d) given in the KS standard (KS B ISO 17660-1). According to AWS D1.4, the preheating temperature was set to $150^{\circ}C$ for D19 and below, and $260^{\circ}C$ for D22 and above. In the test results, the tensile strength of rebars with welded lap joints exceeded the required strength (125% of the yield strength) according to the concrete design code. To analyze the effect of preheating, the tensile strength of the welded rebars after preheating was not significantly different from that of the welded rebars without preheating. The carbon equivalent content (Ceq) of the rebars used in the test was 0.45% or less. Under AWS D1.4, no preheating is required if the carbon equivalent is less than 0.45%. All specimens with a welded lap length of 8d failed by a bar fracture. The effect of preheating was confirmed to be insignificant due to the low carbon equivalent of the rebar.

Flexural Capacity of Precast Concrete Triple Ribs Slab (프리캐스트 콘크리트 트리플 리브 슬래브의 휨성능)

  • Hwang, Seung-bum;Seo, Soo-yeon;Lee, Kang-cheol;Lee, Seok-hyun
    • Journal of the Korea Concrete Institute
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    • v.28 no.1
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    • pp.3-11
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    • 2016
  • The concern about hollow core PC slab has been increased to improve the workability during a construction of building by reducing self weight of structural members. In this manner, recently, TRS (Tripple Ribs Slab) was developed as a new type of half PC slab system. TRS member consists of the triple webs and the bottom flange prestressed by strands. The slab system is completed by casting of topping concrete on the TRS after filling styrofoam between the webs. This paper, presents a flexural experiment to investigate the flexural capacity of the TRS. Five full scale TRS members were made and tested under simple support condition to be failed by flexure and their strength was evaluated by code equations; the variables in the test are the depth and the presence of topping or raised spot formed when slip-forming. In addition, a nonlinear sectional analysis was performed for the specimens and the result was compared with the test results. From the study, it was found that the TRS has enough flexural strength and ductility to resist the design loads and its strength can be suitably predicted by using code equations. The raised spot did not affect the strength so that the spot need not to be removed by doing additional work. For the more accurate prediction of TRS's flexural behavior by using nonlinear sectional analysis, it is recommended to consider the concrete's brittle property due to slip-forming process in the modeling.

Development of a Needs Based Education Course on the Basics of Radiation (수요 분석 기반 방사선 기초 교육과정 개발)

  • Nam, Jong Soo;Won, Jong Yeoul;Seo, Kyung Won;Yoo, Hye Won;Hwang, In Ah
    • Journal of Radiation Protection and Research
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    • v.38 no.2
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    • pp.100-105
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    • 2013
  • With the export of commercial nuclear power plants to UAE and that of a research reactor to Jordan, as well as the additional construction of domestic nuclear power plants, the demand of nuclear manpower is expected to increase sharply. Accordingly, nuclear manpower development is recently becoming an important issue. Major institutes involved in nuclear programs are well equipped with education and training procedures and resources. However, small and medium sized businesses have difficulties to educate their employees due to their limited resources and capacity for the education. Addressing the difficulties, this study is intended to develop and education course in accordance with the "Systematic Approach to Training (SAT)". For this, a survey is conducted on the need of education in small and medium sized businesses, based on which a pilot course on the basics of radiation is developed and operated. An assessment on the development and operation using a survey regarding participants response has shown high grades of performance, i.e. above 4.0 points (full mark: 5.0 points) on each level of expectancy, satisfaction and lecturers' capacity. The experience from this study will be used to develop other programs of nuclear power and ASME code, which are also identified from the need analysis.