bluuebunny/crossref_metadata_2025_split huggingface dataset:
EFFECT OF AIR CONDITION ON AP-1000 CONTAINMENT COOLING PERFORMANCE IN STATION BLACK OUT ACCIDENT
Authors: Tjahjono Hendro 
Published: August 2017

ABSTRACT EFFECT OF AIR CONDITION ON AP-1000 CONTAINMENT COOLING PERFORMANCE IN STATION BLACK OUT ACCIDENT. AP1000 reactor is a nuclear power plant generation III+ 1000 MWe which apply passive cooling concept to anticipate accidents triggered by the extinction of the entire supply of electrical power or Station Black Out (SBO). In the AP1000 reactor, decay heat disposal mechanism conducted passively through the PRHR-IRWST and subsequently forwarded to the reactor containment. Containment externally cooled through natural convection in the air gap and through evaporation cooling water poured on the outer surface of the containment wall. The mechanism of evaporation of water into the air outside is strongly influenced by the conditions of humidity and air temperature. The purpose of this study was to determine the extent of the influence of the air condition on cooling capabilities of the AP1000 containment. The method used is to perform simulations using Matlab-based analytical calculation model capable of estimating the power of heat transfered. The simulation results showed a decrease in power up to 5% for relative humidity rose from 10% to 95%, while the variation of air temperature of 10 °C to 40°C, the power will decrease up to 15%. It can be concluded that the effect of air temperature increase is much more significant in lowering the containment cooling ability compared with the increase of humidity. Keywords: containment cooling, AP1000, air condition, SBO ABSTRAK PENGARUH KONDISI UDARA TERHADAP KINERJA PENDINGINAN SUNGKUP AP-1000 DALAM KECELAKAAN STATION BLACK OUT. Reaktor AP-1000 merupakan PLTN generasi III+ berdaya 1000 MWe yang menerapkan konsep pendinginan pasif untuk mengantisipasi terjadinya kecelakaan yang dipicu oleh padamnya seluruh suplai daya listrik atau dikenal dengan Station Black Out (SBO). Pada reaktor AP-1000, mekanisme pembuangan kalor peluruhan dilakukan secara pasif melalui PRHR yang diteruskan ke IRWST dan selanjutnya pada sungkup reaktor. Sungkup didinginkan secara eksternal melalui konveksi alamiah pada celah udara dan melalui penguapan air pendingin yang diguyurkan di permukaan luar dinding sungkup. Mekanisme penguapan air ke udara luar sangat dipengaruhi oleh kondisi kelembaban dan temperatur udara. Tujuan dari penelitian ini adalah untuk mengetahui sejauh mana pengaruh kondisi udara tersebut terhadap kemampuan pendinginan dari sungkup AP1000. Metode yang digunakan adalah dengan melakukan simulasi menggunakan model perhitungan analitis berbasis Matlab yang mampu mengestimasi daya kalor yang dievakuasi. Hasil simulasi menunjukkan adanya penurunan daya hingga 5% untuk kelembaban relatif naik dari 10% hingga 95%, sedangkan untuk variasi temperatur udara dari 10°C hingga 40°C, daya akan menurun hingga 15%. Dapat disimpulkan bahwa pengaruh kenaikan temperatur udara jauh lebih signifikan dalam menurunkan kemampuan pendinginan sungkup dibandingkan dengan naiknya kelembaban. Kata kunci: pendinginan sungkup, AP1000, kondisi udara, SBO
NEUTRONICS ANALYSIS ON MINI TEST FUEL IN THE RSG-GAS CORE
Authors: Surbakti Tukiran , Sembiring Tagor Malem 
Published: August 2017

Abstract NEUTRONICS ANALYSIS ON MINI TEST FUEL IN THE RSG-GAS CORE. Research of UMo fuel for research reactor has been developing right now. The fuel of research reactor used is uranium low enrichment with high density. For supporting the development of fuel, an assessment of mini fuel in the RSG-GAS core was performed. The mini fuel are U7Mo-Al and U6Zr-Al with densitis of 7.0gU/cc and 5.2 gU/cc, respectively. The size of both fuel are the same namely 630x70.75x1.30 mm were inserted to the 3 plates of dummy fuel. Before being irradiated in the core, a calculation for safety analysis from neutronics and thermohydrolics aspects were required. However, in this paper will discuss safety analysis of the U7Mo-Al and U6Zr-Al mini fuels from neutronic point of view. The calculation was done using WIMSD-5B and Batan-3DIFF code. The result showed that both of the mini fuels could be irradiated in the RSG-GAS core with burn up less than 70 % within 12 cycles of operation without over limiting the safety margin. Power density of U7Mo-Al mini fuel bigger than U6Zr-Al fuel. Key words: mini fuel, neutronics analysis, reactor core, safety analysis Abstrak ANALISIS NEUTRONIK ELEMEN BAKAR UJI MINI DI TERAS RSG-GAS. Penelitian tentang bahan bakar UMo untuk reaktor riset terus berkembang saat ini. Bahan bakar reaktor riset yang digunakan adalah uranium pengkayaan rendah namun densitas tinggi. Untuk mendukung pengembangan bahan bakar dilakukan uji elemen bakar mini di teras reakror RSG-GAS dengan tujuan menentukan jumlah siklus di dalam teras sehingga tercapai fraksi bakar maksimum. Bahan bakar yang diuji adalah U7Mo-Al dengan densitas 7,0 gU/cc dan U6Zr-Al densitas 5,2 gU/cc. Ukuran kedua bahan bakar uji tersebut adalah sama 630x70,75x1,30 mm dimasukkan masing masing kedalam 3 pelat dummy bahan bakar. Sebelum diiradiasi ke dalam teras reaktor maka perlu dilakukan perhitungan keselamatan baik secara neutronik maupun termohidrolik. Dalam makalah ini akan dibahas analisis keselamatan uji bahan bakar mini U7Mo-Al dan U6Zr-Al ditinjau dari segi neutronik. Perhitungan dilakukan dengan menggunakan program komputer WIMSD-5B dan Batan-3DIFF. Hasil analisis menunjukkan bahwa kedua bahan bakar uji dapat diiradiasi dengan derajat bakar < 70 % selama 12 siklus operasi tanpa melampaui batas keselamatan neutronik. Kerapatan panas bahan bakar uji U7Mo-Al lebih besar dari bahan bakar U6Zr-Al. Kata kunci: Bahan bakar mini, analisis neutronik, teras reaktor, analisis keselamatan
INVESTIGATION OF RDE THERMAL PARAMETERS CHANGES IN RESPONSE TO LONG-TERM STATION BLACK OUT
Authors: Tjahjono Hendro 
Published: August 2017

Due to long-term station black out (SBO) of the RDE (Experimental Power Reactor), the residual heat from the core will be removed to a residual heat removal system (RHRS). The objective of this study is to know the transient characteristic of RDE thermal parameters in response to the loss of residual heat removing ability for long-term. To achieve this objective, an analysis model of reactor thermal parameters changes during SBO, using Matlab program to simulate heat transfer equations of conduction, convection and radiation has been performed. Using this program, the changes of RDE thermal parameters until 800 hours after reactor trip have been analyzed. It is concluded that, in long-term SBO condition, the reactor is still safe with the maximum core temperature of 1140°C, which is still far under the safety limit of 1600°C as stated in the design criteria. More attentions are needed to be taken with the increasing of concrete temperature up to 600°C when the water storage is empty. Therefore, the availability of water in the RHRS shall absolutely be maintained.Keywords: experimental power reactor, residual heat removal, transient, Matlab. INVESTIGASI PERUBAHAN PARAMETER TERMAL RDE PADA KONDISI KEHILANGAN CATU DAYA LISTRIK DALAM JANGKA PANJANG. Akibat kehilangan catu daya listrik luar pada Reaktor Daya Eksperimental (RDE), panas sisa dari reaktor dibuang ke suatu sistem pembuang panas sisa. Penelitian ini bertujuan untuk mengetahui karakteristik transien parameter termal RDE ketika terjadi kegagalan pembuangan kalor sisa tersebut dalam jangka panjang. Untuk mencapai tujuan tersebut telah disusun model analisis perubahan parameter termal reaktor ketika terjadi Station Black Out (SBO) menggunakan pemrograman Matlab dengan melibatkan persamaan-persamaan perpindahan kalor secara konduksi, konveksi dan radiasi. Dengan menggunakan program ini perubahan parameter termal RDE hingga 800 jam setelah reaktor trip telah dianalisis. Disimpulkan bahwa pada kondisi SBO dalam jangka panjang tersebut, reaktor masih tetap aman dengan temperatur maksimum teras sebesar 1140 °C, yaitu masih jauh di bawah batas aman 1600 °C yang telah ditetapkan dalam kriteria desain. Perlu diperhatikan adanya peningkatan temperatur beton hingga 600 °C jika air pendingin sudah habis. Oleh karena itu, ketersediaan air pendingin di sistem pembuang panas sisa mutlak harus dijaga.Kata kunci: reaktor daya eksperimental, pembuang panas sisa, transien, Matlab.
PARAMETRIC STUDY OF LOCA IN TRIGA-2000 USING RELAP5/SCDAP CODE
Authors: Antariksawan Anhar Riza , Widodo Surip , Tjahjono Hendro 
Published: August 2017

A postulated loss of coolant accident (LOCA) shall be analyzed to assure the safety of a research reactor. The analysis of such accident could be performed using best estimate thermal-hydraulic codes, such as RELAP5. This study focuses on analysis of LOCA in TRIGA-2000 due to pipe and beam tube break. The objective is to understand the effect of break size and the actuating time of the emergency core cooling system (ECCS) on the accident consequences and to assess the safety of the reactor. The analysis is performed using RELAP/SCDAPSIM codes. Three different break size and actuating time were studied. The results confirmed that the larger break size, the faster coolant blow down. But, the siphon break holes could prevent the core from risk of dry out due to siphoning effect in case of pipe break. In case of beam tube rupture, the ECCS is able to delay the fuel temperature increased where the late actuation of the ECCS could delay longer. It could be concluded that the safety of the reactor is kept during LOCA throughout the duration time studied. However, to assure the integrity of the fuel for the long term, the cooling system after ECCS last should be considered. Keywords: safety analysis, LOCA, TRIGA, RELAP5 STUDI PARAMETRIK LOCA DI TRIGA-2000 MENGGUNAKAN RELAP5/SCDAP. Kecelakaan kehilangan air pendingin (LOCA) harus dianalisis untuk menjamin keselamatan suatu reaktor riset. Analisis LOCA dapat dilakukan menggunakan perhitungan best-estimate seperti RELAP5. Penelitian ini menekankan pada analisis LOCA di TRIGA-2000 akibat pecahnya pipa dan tabung berkas. Tujuan penelitian adalah memahami efek ukuran kebocoran dan waktu aktuasi sistem pendingin teras darurat (ECCS) pada sekuensi kejadian dan mengkaji keselamatan reaktor. Analisis dilakukan menggunakan program perhitungan RELAP/SCDAPSIM. Tiga ukuran kebocoran dan waktu aktuasi ECCS berbeda dipilih sebagai parameter dalam studi ini. Hasil perhitungan mengonfirmasi bahwa semakin besar ukuran kebocoran, semakin cepat pengosongan tangki reaktor. Lubang siphon breaker dapat mencegah air terkuras dalam hal kebocoran pada pipa. Sedang dalam hal kebocoran pada beam tube, ECCS mampu memperlambat kenaikan temperatur bahan bakar. Dari studi ini dapat disimpulkan bahwa keselamatan reaktor dapat terjaga pada kejadian LOCA, namun pendinginan jangka panjang perlu dipertimbangkan untuk menjaga integritas bahan bakar.Kata kunci: analisis keselamatan, LOCA, TRIGA, RELAP5
OPTIMASI PENGGUNAAN HCl SEBAGAI LARUTAN PENGELUSI ITRIUM-90 DALAM DOWEX® 50WX8-200
Authors: Sulaiman Sulaiman , Aguswarini Sri , Karyadi Karyadi , Chairuman Chairuman , S Gatot , Subur M , G Adang H 
Published: August 2017

OPTIMASI PENGGUNAAN HCl SEBAGAI LARUTAN PENGELUSI ITRIUM-90 DALAM DOWEX® 50WX8-200. Itrium-90 merupakan radionuklida pemancar β yang mempunyai waktu paruh 64,1 jam dan memancarkan energi β maksimum 2280 keV. Itrium-90 digunakan dalam kedokteran nuklir untuk keperluan terapi. Sistem generator 90Sr/90Y telah dikembangkan untuk mendapatkan 90Y bebas pengemban. Itrium-90 yang diperoleh dari generator 90Sr/90Y berbentuk radiokimia 90Y-sitrat. Bentuk radiokimia 90Y yang ideal untuk penandaan berbagai macam ligan yaitu 90YCl3. Untuk mendapatkan bentuk radiokimia 90Y yang diinginkan dilakukan serangkaian proses dengan metode penukar ion menggunakan resin Dowex® 50WX8-200. Dalam penelitian ini telah dilakukan optimasi penggunaan HCl untuk elusi 90Y dari resin dengan variasi konsentrasi HCl dan waktu kontak saat elusi 90Y dari resin. Pelepasan 90Y dari resin Dowex® 50WX8-200 tergantung pada konsentrasi HCl yang digunakan. Konsentrasi HCl semakin besar laju pelepasan 90Y dari 90Y-Dowex semakin besar. Waktu kontak optimummenggunakan 5 mL HCl 12 N adalah 60 menit dengan hasil 9,4 %. Hasil uji 90Y setelah dielusi dari Dowex® 50WX8-200 memberikan informasi radionuklida 90Y yang diperoleh dalam bentuk radiokimia 90YCl3. OPTIMIZATION OF USE HCl AS SOLUTION FOR ELUTION ITRIUM-90 IN DOWEX® 50WX8- 200. Yttrium-90 is a β emitter radionuclide with a half life of 64.1 hours and emits the maximum β energy at 2280 keV. Yttrium-90 radionuclide is widely used in nuclear medicine for therapeutic purposes. 90Sr/90Y generator system has been developed to obtain carrier-free 90Y. Yttrium-90 were obtained from the 90Sr/90Y generator in the form of 90Y-citrate radiochemical. The 90Y ideal for tagging ligands is in the form of 90YCl3. To obtain the desired radiochemical a series of processes with ion exchange resin method is performed using Dowex® 50WX8-200. In this study optimization of the use of HCl for has been carried out 90Y elution from the resin with varied HCl concentration and contact time when 90Y is eluted from the resin. The release of 90Y from resin Dowex® 50WX8-200 depending on the concentration of HCl is used. The greater the concentration of HCl release rate of 90Y from 90Y-Dowex greater. The optimum contact time with 5 mL of 12 N HCl is 60 minutes with a result of 9.4%. The 90Y test results after eluted from Dowex® 50WX8-200 indicated that the 90Y was in the form of 90YCl3.
PEMISAHAN Zr – Hf SECARA SINAMBUNG MENGGUNAKAN MIXER SETTLER
Authors: Biyantoro Dwi , Isyuniarto Isyuniarto , Masrukan Masrukan 
Published: August 2017

PEMISAHAN Zr – Hf SECARA SINAMBUNG MENGGUNAKANMIXER SETTLER. Telah dilakukan pemisahanZr – Hf secara sinambung menggunakan pengaduk pengenap (mixer settler) 16 stage. Larutan umpan adalah zirkon nitrat dengan kadar Zr = 30786 ppm dan Hf = 499 ppm. Ekstraktan dipakai adalah solven 60 % TBP dalam kerosen dan larutan scrubbingyang dipakai adalah asam nitrat 1 M. Umpan masuk pada stageke 5 dikontakkan secara berlawanan arah dengan solven masuk pada stage ke 16 dan larutan scrubbing masuk pada stage ke 1. Tujuan penelitian ini adalah memisahkan unsur Zr dan Hf dari hasil olah pasir zirkon menggunakan solven TBP dengan alat mixer settler16 stage. Analisis umpan dan hasil proses pemisahan untuk zirkonium (Zr) dilakukan dengan menggunakan alat pendar sinar-X, sedangkananalisis unsur hafnium (Hf) menggunakan Analisis Pengaktifan Neutron (APN). Parameter penelitian dilakukan dengan variasi keasaman asam nitrat dalam umpan dan variasi waktu pada berbagai laju pengadukan. Hasil penelitian pemisahan unsur Zr dengan Hf diperolehkondisi optimum pada keasaman umpan 4 N HNO3, keseimbangan dicapai setelah 3jam dan laju pengadukan 3300 rpm. Hasil ekstrak unsur zirkon (Zr) diperoleh kadar sebesar 28577 ppm dengan efisiensi 92,76 % serta kadar pengotor hafnium (Hf) sebesar 95 ppm.Kata Kunci: pemisahan Zr, Hf, ekstraksi, mixer settler, alat pendar sinar-X, APN. SEPARATION of Zr - Hf CONTINUOUSLY USE THE MIXER SETTLER. Separation of Zr - Hf continuously using mixer settler 16 stage has been done. The feed solution is zircon nitrate concentration of Zr = 30786 ppm and Hf = 499 ppm. As the solvent used extractant 60 % TBP in 40 % kerosene. Nitric acid solution used srubbing 1 M. The feed entered into stage to 5 is contacted with solvents direction on the stage to 16 and the scrubbing solution enter the stage to 1. The purpose of this study is to separate Zr and Hf of the results from the process of zircon sand using solvent TBP using 16 stage mixer settler. Analysis of the feed and the results of the separation process for zirconium (Zr) using X-ray fluorescence instrument which hafnium (Hf) using Neutron Activation Analysis (AAN). Parameter study done of acidity variation of nitric acid in the feed and time variation in various stirring speed. From the research the separation of Zr-Hf, the optimum conditions in acidity feed 4 N HNO3, equillibrium was received after 3 hours, and stirring speed of 3300 rpm obtained extract of zircon (Zr) concentration = 28577 ppm (effisiency of Zr = 92,76 %)with impurities of hafnium (Hf) = 95 ppm.Keywords: separation of Zr, Hf, extraction, mixer settlers, X-ray fluorescence, NAA.
USE OF MEMBRANE EMULSION SPAN 80 AND TOPO IN URANIUM EXTRACTION AND STRIPPING
Authors: Basuki Kris Tri , Nurimaniwathy Nurimaniwathy , Puspita Dian , H.B Bambang E 
Published: August 2017

USE OF MEMBRANE EMULSION SPAN 80 AND TOPO IN URANIUM EXTRACTION AND STRIPPING. Membrane emulsion span 80 and TOPO used in uranium extraction and stripping has been done. The extraction was carried outby emulsion membrane H3PO4 in TOPO-Kerosene. The feed or external aqueous phase was uranium in HNO3. The emulgator span-80 was used to obtain a stable emulsion membrane system. The influence factors were percentage of TOPO-Kerosene, time extraction, molarity of external aqueous phase and molarity of internal aqueous. After the emulsion membrane was formed, the extractionand stripping process was performed. The ratio volume feed : volume membrane phase equal to 1 : 1 and volume of 5 % TOPO-Kerosene : Volume 3 M H3PO4 equal 1 : 1 were used. The relative good yield were obtained at concentration of TOPO in Kerosene and 3 M H3PO4 was 5 %, molarity of internal aqueous phase equal to 1 M, molarity of external aqueous phase 3 M H3PO4 and time extraction equalto 10 minutes with the speed of emulsification was 8000 rpm. At this condition the extraction efficiency of uranium obtained was 97.8 %, the stripping efficiency 52.56 %, and the total efficiency was 53.80 %.Keywords: membrane emulsion, extraction, stripping, span 80, kerosene, uranium. PENGGUNAAN MEMBRAN EMULSI SPAN 80 DAN TOPO UNTUK EKSTRASI DAN STRIPPING URANIUM. Telah dilakukan penelitian membran emulsi span 80 dan TOPO yang digunakan untuk ekstraksi uranium. Extraksi dengan membran emulsi H3PO4 dalam TOPO-Kerosen. Larutan umpan untuk fasa air eksternal adalah uranium dalam asam nitrat. Untuk memperoleh sistem emulsi yang stabil dipakai emulgator Span 80. Parameter yang berpengaruh adalah persen TOPO-Kerosene, molaritas fasa air internal H3PO4, molaritas fasa air eksternal HNO3 dan waktu ekstraksi. Setelah diperoleh membran emulsi, kemudian dilakukan proses ekstraksi dan stripping, dengan rasio volume umpan : volume membran sebesar 1 : 1; volume 5% TOPO-Kerose : volume 3M H3PO4 sebesar 1 : 1. Hasil relatif lebih baik diperoleh pada konsen-trasi TOPO Kerosene: volume 3 M H3PO4 adalah 5 %, molaritas larutan fasa internal sebesar 1 M, molaritas larutan fasa eksternal adalah 3 M H3PO4 dan waktu ekstraksi sebesar 10 menit dengan kecepatan emulsi 8000 rpm. Pada kondisi ini diperoleh effisiensi ekstraksi uranium 97,8 %, efisiensi stripping 52,56 % dan efisiensi total adalah 53,8 %.Kata Kunci : membran emulsi, ekstraksi, stripping, span 80, kerosen, uranium.
FORTALECIMENTO MUSCULAR EXCÊNTRICO NO TRATAMENTO DA TENDINOPATIA DE AQUILES: UMA REVISÃO SISTEMÁTICA
Authors: Silva Wanderson Fernandes , Marques da Rocha Guilherme , De Aquina Vieira Filho Walter , Marques da Rocha Gustavo , Fernandes Silva Angelina , Guimarães Corrêa Augusto 
Published: August 2017

INTRODUÇÃO: A Fisioterapia, no manejo da tendinopatia de Aquiles, utiliza-se de recursos físicos moduladores da inflamação e analgésicos. Como parte do tratamento fisioterapêutico a literatura tem sugerido o exercício de fortalecimento excêntrico com eficaz na resolução de tendinopatias. OBJETIVO: O presente estudo teve como objetivo a busca de evidências científicas sobre o uso do exercício de fortalecimento excêntrico no manejo da Tendinopatia de Aquiles. MÉTODOS: Para a composição da revisão foi realizada busca por estudos nas base de dados virtuais Pubmed e PEDro. Os descritores utilizados foram as seguintes: Eccentric, tendinopathy, Achilles Tendonitis. Para compor o estudo os artigos deveriam obedecer os seguintes critérios de elegibilidade: artigos publicados na língua inglesa, intervalo de publicação entre 2013 a 2017, ensaios clínicos randomizados, com pontuação superior a 6 na escala de qualidade PEDro. RESULTADOS: Foram localizados um total de 87 artigos, dos quais apenas 21 referiam-se a temática em questão. Dos 21 artigos 14 foram excluídos pelos seguintes motivos: 3 por consistirem em relatos de caso, 1 classificado como revisão de literatura, 1 caracterizava-se como comentário clinico, 1 envolvia um estudo com modelo animal, 1 era um projeto de pesquisa, 5 não classificavam-se com ensaios clínicos randomizados, 1 obteve nota inferior a 6 na escala de qualidade PEDro e 1 deles proporcionava descrição incompleta dos resultados. CONCLUSÃO: O fortalecimento muscular excêntrico caracteriza-se como uma modelo terapêutico de escolha para o manejo da tendinopatia de aquiles, a combinação com outras modalidades potencializa seus efeitos fisiológicos.
Capital social e turismo rural em uma associação do norte do Rio Grande do Sul: um estudo da Rota das Salamarias
Authors: Dos Santos Jaqueline , Melara Fabiana , Severo Eliana Andréa , Macke Janaina 
Published: August 2017

Resumo O capital social é a soma dos recursos reais e potenciais de uma rede de relacionamentos de uma unidade individual ou social. O objetivo com a presente pesquisa foi entender como o capital social contribui para o desenvolvimento do turismo rural na Associação Rota das Salamarias, localizada na região Norte do Rio Grande do Sul. A pesquisa caracteriza-se como qualitativa, tendo como abordagem o estudo de caso, e quanto ao propósito pode ser definida como descritiva. Para a coleta de dados realizaram-se entrevistas semiestruturadas. Posteriormente, as entrevistas foram integralmente transcritas e realizou-se análise de conteúdo. Entre os principais resultados obtidos se destaca o fato de o turismo rural ser uma estratégia de desenvolvimento local que contribui para a geração de renda e para a manutenção das famílias em suas propriedades, fortalece o empreendedorismo familiar e amplia a relação entre as famílias que compõem a Rota. Também, identificou-se a relevância do crescimento econômico e do capital social reconhecido no formato de interação social proporcionado pela referida Associação, visto que essa coesão social fundamenta a construção de vantagens competitivas sustentáveis, dado que o conhecimento é adquirido e transmitido a todos que fazem parte da rede de parceiros, gerando riquezas para as propriedades e para a região da qual fazem parte.Palavras-chave: Capital social. Turismo rural. Associação Rota das Salamarias. Vantagens competitivas. Abstract Social capital is the sum of the actual and potential resources of a network of relationships of individual or social unit. The aim of this research was to understand how the social capital contributes for the development of rural tourism in Rota das Salamarias. The research is characterized as qualitative, with the approach of the case study, and regarding the purpose it can be defined as descriptive. For data collection semi-structured interviews were carried out. Subsequently, the interviews were fully transcribed and the content analysis was performed. Among the main findings stands out the fact that rural tourism is a local development strategy that contributes for the income generation and for the maintenance of families in their properties, strengthens the family entrepreneurship and expands the relationship between the families that make up the route. Also, it was identified the importance of economic growth and the social capital recognized in the interaction format provided by that Association, since this social cohesion supports the building of the sustainable competitive advantages, since knowledge is acquired and transmitted to everyone who is part of the network of partners, generating wealth for the properties and for the region to which they belong.Keywords: Social capital. Rural tourism. Association Rota das Salamarias. Competitive advantages.