• Title/Summary/Keyword: Water and energy cycle

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Comparative Performance Analysis of Ammonia-Water Rankine Cycle and Kalina Cycle for Recovery of Low-Temperature Heat Source (저온 열원 발전을 위한 암모니아-물 랭킨 사이클과 칼리나 사이클의 성능특성의 비교 해석)

  • KIM, KYOUNGHOON;BAE, YOOGEUN;JUNG, YOUNGGUAN;KIM, SEWOONG
    • Journal of Hydrogen and New Energy
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    • v.29 no.2
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    • pp.148-154
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    • 2018
  • This paper presents a comparative analysis of thermodynamic performance of ammonia-water Rankine cycles with and without regeneration and Kalina cycle for recovery of low-temperature heat source. Special attention is paid to the effect of system parameters such as ammonia mass fraction and turbine inlet pressure on the characteristics of the system. Results show that maximum net power can be obtained in the regenerative Rankine cycle for high turbine inlet pressures. However, Kalina cycle shows better net power and thermal efficiency for low turbine inlet pressures, and the optimum ammonia mass fractions of Kalina cycle are lower than Rankine cycles.

A Study on Regenerative OTEC System using the Condenser Effluent of Uljin Nuclear Power Plant (울진 원자력발전소 온배수를 이용한 재생식 해양온도차발전에 대한 연구)

  • Kang, Yun-Young;Park, Sung-Seek;Park, Yun-Beom;Kim, Nam-Jin
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.24 no.7
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    • pp.591-597
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    • 2012
  • For the past few years, the concern for clean energy has been greatly increased. Ocean thermal Energy Conversion(OTEC) power plants are studied as a viable option for the supply of clean energy. In this study, we examined the thermodynamic performance of the OTEC power system for the production of electric power. Computer simulation programs were developed under the same condition and various working fluids for closed Rankine cycle, regenerative cycle, Kalina cycle, open cycle, and hybrid cycle. The results show that the regenerative cycle showed the best system efficiency. And then we examined the thermodynamic performance of regenerative cycle OTEC power system using the condenser effluent from Uljin nuclear power plant instead of the surface water. The highest system efficiency of the condition was 4.55% and the highest net power was 181 MW.

Hydrogen Prodution by Sulfur Thermochemical Water Splitting Cycle: Part 1. H2O-SO2-I2 Reaction and Separation (황 - 요오드의 열화학적 물분리에 의한 수소제조연구 Part I. 물-이산화황-요오드 반응 및 분리)

  • Lee, K.I.;Min, B.T.;Kwon, S.G.;Kang, Y.H.
    • Journal of Hydrogen and New Energy
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    • v.1 no.1
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    • pp.40-47
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    • 1989
  • The sulfur-iodine thermochemical water splitting process of GA(General atomic) cycle was studied to produce hydrogen from water by $H_2-I_2-SO_2$ reactions. The experimental scale was 500g based on iodine. The reaction took 100 minutes, products could be separated two liquid phases due to their density difference:HI solution had a density of 2.39~2.61g/cc, and $H_2SO_4$ solution had 1.37~1.38g/cc. The condition of reaction was when weight ratio of $I_2/H_2O$ was 2/1 resulting in good phase separation and productivity.

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Energy optimization of a Sulfur-Iodine thermochemical nuclear hydrogen production cycle

  • Juarez-Martinez, L.C.;Espinosa-Paredes, G.;Vazquez-Rodriguez, A.;Romero-Paredes, H.
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.2066-2073
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    • 2021
  • The use of nuclear reactors is a large studied possible solution for thermochemical water splitting cycles. Nevertheless, there are several problems that have to be solved. One of them is to increase the efficiency of the cycles. Hence, in this paper, a thermal energy optimization of a Sulfur-Iodine nuclear hydrogen production cycle was performed by means a heuristic method with the aim of minimizing the energy targets of the heat exchanger network at different minimum temperature differences. With this method, four different heat exchanger networks are proposed. A reduction of the energy requirements for cooling ranges between 58.9-59.8% and 52.6-53.3% heating, compared to the reference design with no heat exchanger network. With this reduction, the thermal efficiency of the cycle increased in about 10% in average compared to the reference efficiency. This improves the use of thermal energy of the cycle.

Thermodynamic Analysis of Power Generation Cycle Utilizing LNG Cold Energy (LNG 냉열을 이용하는 동력사이클 열역학 해석)

  • 최권일;장홍일
    • Progress in Superconductivity and Cryogenics
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    • v.1 no.1
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    • pp.48-55
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    • 1999
  • thermodynamic cycle analysis has been performed for the power generation systems to utilize the cold energy of liquefied natural gas (LNG). The power cycle used the air or water at room temperature as a heat source and the LNG at cryogenic temperature as a heat sink. Among manypossible configurations of the cycle. the open Rankine cycle. and the closed Brayton cycle, and the closed Rankine cycle are selected for the basic analysis because of their practical importance. The power output per unit mass of LNG has been analytically calculated for various design parameters such as the pressure ratio. the mass flow rate. the adiabatic efficiency. the heat exchanger effectiveness. or the working fluid. The optimal conditions for the parameters are presented to maximize the power output and the design considerations are discussed. It is concluded that the open Rankine cycle is the most recormmendable both in thermodynamic efficency and in practice.

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Two-Step Thermochemical Cycle with Supported $NiFe_2O_4$ for Hydrogen Production (지지체의 변화에 따른 Ni-페라이트의 2단계 열화학 사이클 반응 특성에 관한 연구)

  • Kim, Woo-Jin;Kang, Kyoung-Soo;Kim, Chang-Hee;Choi, Won-Chul;Kang, Yong;Park, Chu-Sik
    • Journal of Hydrogen and New Energy
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    • v.19 no.6
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    • pp.505-513
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    • 2008
  • The two-step thermochemical cycle was examined on the $CeO_2$, YSZ, and $ZrO_2$-supported $NiFe_2O_4$ to investigate the effects of support material addition. The supported $NiFe_2O_4$ was prepared by the aerial oxidation method. Thermal reduction was conducted at 1573K and 1523K while water-splitting was carried out at 1073K. Supporting $NiFe_2O_4$ on $CeO_2$, YSZ and $ZrO_2$ alleviated the high-temperature sintering of iron-oxide. As a result, the supported $NiFe_2O_4$ exhibited greater reactivity and repeatability in the water-splitting cycle as compared to the unsupported $NiFe_2O_4$. Especially, $ZrO_2$-supported $NiFe_2O_4$ showed better sintering inhibition effect than other supporting materials, but hydrogen production amount was decreased as cycle repeated. In case of $CeO_2$-supported $NiFe_2O_4$, improvement of hydrogen production was found when the thermal reduction was conducted at 1573K. It was deduced that redox reaction of $CeO_2$ activated above 1573K.

Fuel Cycle Analysis of Heavy Water-Moderated Reactor System

  • Paik, In-Kul;Kim, Jin-Soo;Lee, Chang-Kun;Chung, Chang-Hyun;Kim, Chang-Hyo
    • Nuclear Engineering and Technology
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    • v.9 no.1
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    • pp.15-31
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    • 1977
  • New conception of batch and period is defined appropriate for the on-power refuelling scheme of a heavy water-moderated reactor, A computer code (“HWRCOST”) is developed using nuclear fuel cycle economic equations based on the continuous energy calculation method. The fuel cycle cost of the CANDU-PHW reactor is calculated and sensitivity analyses are performed with variation of uranium ore price, fabrication cost, spent fuel permanent disposal expenses, and capacity fctor.

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Performance Characteristics and Economic Assessment of Heat Pump Systems with the Various Heat Source (열원에 따른 열펌프의 성능 비교 및 경제성 평가)

  • Park, Cha-Sik;Park, Kyoung-Woo;Kwon, Oh-Kyung
    • Journal of the Korean Society for Geothermal and Hydrothermal Energy
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    • v.7 no.1
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    • pp.23-31
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    • 2011
  • The objectives of this study are to analyze the performance of a heat pump system with the various heat source and to carry out economic assessment for the heat pump system. The COP of the river water and ground source heat pump system was 20% higher than that of the air source heat pump system because river water and geothermal provide stable operating temperature compared with air temperature throughout the year. In addition, the economic assessment of a heat pump system using air, river water, and geothermal as a heat source was carried out. The ratio of the life cycle operating cost to the life cycle cost increased with the increase of building capacity. The payback period was found to be less than 3.3 and 4.5 years, respectively when the capacity of the river water and ground source heat pump was larger than 10 RT.

Exergy Analysis of Regenerative Wet-Compression Gas-Turbine Cycles (습식 압축을 채용한 재생 가스터빈 사이클의 엑서지 해석)

  • Kim, Kyoung-Hoon;Kim, Se-Woong;Ko, Hyung-Jong
    • Journal of Energy Engineering
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    • v.18 no.2
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    • pp.93-100
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    • 2009
  • An exergy analysis is carried out for the regenerative wet-compression Brayton cycle which has a potential of enhanced thermal efficiency owing to the reduced compression power consumption and the recuperation of exhaust energy. Using the analysis model, the effects of pressure ratio and water injection ratio are investigated on the exergy efficiency of system, exergy destruction ratio for each component of the system, and exergy loss ratio due to exhaust gas. The results of computation for the typical cases show that the regenerative wet-compression gas turbine cycle can make a notable enhancement of exergy efficiency. The injection of water results in a decrease of exergy loss of exhaust gas and an increase of net power output.

Preliminary Design of the Supercritical $CO_2$ Brayton Cycle Energy Conversion System (초임계 이산화탄소 Brayton 에너지 전환계통 예비설계)

  • Cha, Jae-Eun;Eoh, Jae-Hyuk;Lee, Tae-Ho;Sung, Sung-Hwan;Kim, Tae-Woo;Kim, Seong-O;Kim, Dong-Eok;Kim, Moo-Hwan
    • Proceedings of the KSME Conference
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    • 2008.11b
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    • pp.3181-3188
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    • 2008
  • The supercritical $CO_2$ Brayton cycle energy conversion system is presented as a promising alternative to the present Rankine cycle. The principal advantage of the S-$CO_2$ gas is a good efficiency at a modest temperature and a compact size of its components. The S-$CO_2$ Brayton cycle coupled to a SFR also excludes the possibilities of a SWR (Sodium-Water Reaction) which is a major safety-related event, so that the safety of a SFR can be improved. KAERI is conducting a feasibility study for the supercritical carbon dioxide (S-$CO_2$) Brayton cycle power conversion system coupled to KALIMER(Korea Advanced LIquid MEtal Reactor). The purpose of this research is to develop S-$CO_2$ Brayton cycle energy conversion systems and evaluate their performance when they are coupled to advanced nuclear reactor concepts of the type under investigation in the Generation IV Nuclear Energy Systems. This paper contains the research overview of the S-$CO_2$ Brayton cycle coupled to KALIMER-600 as an alternative energy conversion system.

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