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"In future the UK's energy supplies, for both heat and power, will come from much more diverse sources. In many cases this will mean local energy projects serving a local community or even a single house. What technologies are available? Where and at what scale can they be used? How can they work effectively with our existing energy networks? This book explores these power and heat sources, explains the characteristics of each and examines how they can be used."

"A cement plant that produces 8,300 tons per day releases 265,000 Nm3/h of flue gas at 360°C from its Suspension Preheater (SP) and 400,000 Nm3/h of hot air at 310°C from its air quenching cooler (AQC). It is imperative to recover the waste heat emitted by the plant for power generation, i.e., Waste Heat Recovery Power Generation (WHRPG). This paper aims to optimize waste heat recovery from the cement plant using Response Surface Methodology (RSM), for which an Organic Rankine Cycle (ORC) is applied for electric power generation. The working fluid of an ORC power generation system was selected among candidates of organic working fluids (i.e., isobutane, isopentane, benzene, and toluene) by using the Technique for Order of Preference by Similarity to Ideal Solution (TOPSIS), a Multi-Criteria Decision Analysis (MCDA) method. The ORC power generation system configuration and the corresponding operating conditions employing the selected working fluid (i.e., pressures and temperatures) are optimized by applying RSM. Based on TOPSIS evaluation and considering factors of health, safety, environment impacts, cost, and power generated, isopentane was selected as the working fluid for the ORC WHRPG, which was configured to consist of a boiler, two expansion turbines, a reheater, and a recuperator. Implementation of RSM attained optimum operating conditions of high pressure turbine, low pressure turbine, and condenser at 11.3 bar-a saturated vapor, 4.3 bar-a and 184°C, and 1.8 bar-a, respectively. Finally, the gross electric power generated of 5.7 MW at 12.5 percent of energy conversion efficiency is generated by the pertinent ORC WHRPG."

"ABSTRAKNuklir adalah salah satu sumber energi baru yang patut dipertimbangkan untuk memenuhi kebutuhan energi nasional. Penggunaan bahan nuklir berbasis thorium oksida ThO2 telah dikembangankan oleh beberapa negara maju sebagai bahan bakar nuklir untuk mengurangi dan menggantikan pemakaian uranium yang banyak digunakan sebagai bahan bakar untuk pembangkit listrik tenaga nuklir PLTN di dunia. Pada saat ini Batan Tenaga Nuklir Nasional BATAN berusaha merancang suatu reaktor daya eksperimental RDE dari turunan reaktor tipe High Temperature Gas-cooled Reactor HTGR . Reaktor nuklir tipe HTGR mempunyai dua bentuk bahan bakar yaitu prismatik dan bola pebble . RDE yang akan dikembangkan di Indonesia mempunyai bahan bakar uranium dan atau thorium berbentuk bola. Dalam penelitian ini dilakukan pemodelan dan simulasi panas pembangkitan oleh reaksi fisi yang disebabkan oleh neutron, dan perpindahan panas antara bahan bakar bentuk pebble dengan media pendingin gas helium pada reaktor daya eksperimental. Analisis neutronik dan termal-aliran dalam teras RDE seperti ini belum pernah dilakukan di Indonesia. Tujuan dilakukannya penelitian ini adalah untuk memperoleh desain teras yang aman pada kondisi neutronik yang kritis dari teras RDE. Pemodelan dan simulasi transport partikel neutron untuk analisis pembangkitan panas reaksi fisi dilakukan dengan perangkat lunak berbasis metoda monte carlo-MCNP, dan untuk fenomena transport dalam proses pendinginan RDE dilakukan dengan perangkat lunak komputasi dinamika fluida FLUENT 6.3. Teras aktif RDE dimodelkan dengan geometri silinder berdiameter 180 cm dan tinggi 197 cm. MCNP dapat memodelkan struktur geometri bahan bakar bola dalam teras reaktor RDE dengan baik untuk mensimulasikan transport neutron dan distribusi reaksi fisi. Aliran pendingin gas helium melalui bola-bola bahan bakar dalam teras reaktor dimodelkan sebagai aliran fluida dalam medium berpori. Tiga mode perpindahan panas dan aliran turbulen pendingin dimodelkan dalam proses pendinginan. Dari pemodelan dan simulasi neutronik diperoleh nilai kritikalitas keff =1.0921 dan densitas daya yang dihasilkan sebesar 2.03 watts/cm3. Hasil ini kemudian dimasukkan dalam pemodelan proses pendinginan dan aliran fluida dalam teras RDE sehingga menghasilkan temperatur maksimum pendingin gas helium sebesar 970.32K. Kritikalitas neutronik keff lebih dari satu, tetapi tak melebihi 1,3 dan kondisi termal teras menunjukkan bahwa desain teras RDE sangat aman.

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ABSTRACTNuclear is one of new energy sources that should be considered to meet national energy demands. The usage of Thorium Oxide ThO2 based nuclear fuel has been developed by some developed countries to reduce and replace Uranium that was commonly used as nuclear fuel for nuclear power plants in the world. Nowdays, BATAN is trying to design an experimental power reactor RDE which is the derivative type of High Temperature Gas cooled Reactor HTGR . HTGR has two types of fuel i.e. Prismatic and Pebble. RDE, which will be developed in Indonesia uses spherical uranium and or thorium as its fuel. This research performs modeling and simulation of fission heat generation caused by neutronas well heat transfer between fuel pebble and helium gas as cooling medium in the experimental power reactor. This thermal flow analysis in the RDE core has never been conducted in Indonesia. The objective of this study is to obtain a safe reactor core design in critical neutronic condition of the RDE core. Modeling and simulation of neutron particle transport for fission heat generation analysis were conducted using a software based on Monte Carlo method MCNP, and for the transport phenomena in the cooling process of RDE was conducted using computational fluid dynamics software FLUENT 6.3.26. RDE active core was modeled using cylindrical geometry with a diameter of 180 cm and 197 cm high. MCNP can model the geometrical structure of the Pebble fuel within the RDE core properly to simulate neutron transport and distribution of fission reaction. Flow of helium gas coolant through the pebble fuel in the reactor core was modeled as a fluid flow in a porous medium. Three types of heat transfer and turbulent coolant flow were modeled in the cooling process. Results obtained from Neutronic modeling and simulation i.e. criticality values of 1.0921 keff and average power density of 2.03 watts cm3. These results were later inserted into the cooling process and fluid flow modeling in the RDE core, so that generate the maximum temperature of the coolant helium gas at about 970.32 K. Neutronic criticality more than one, but not exceeding 1.3 and the core thermal conditions showed that the design of the RDE core is very safe."

"This book focuses on the two-phase flow problems relevant in the automotive and power generation sectors. It includes fundamental studies on liquid-gas two-phase interactions, nucleate and film boiling, condensation, cavitation, suspension flows as well as the latest developments in the field of two-phase problems pertaining to power generation systems. It also discusses the latest analytical, numerical and experimental techniques for investigating the role of two-phase flows in performance analysis of devices like combustion engines, gas turbines, nuclear reactors and fuel cells. The wide scope of applications of this topic makes this book of interest to researchers and professionals alike."