Article Per Year (5 Year)
p-Index From 2019 - 2024
1.259
P-Index
This Author published in this journals
All Journal Jurnal Ilmu Dasar Publika Budaya Jurnal Teori dan Aplikasi Fisika Jurnal Fisika Indonesia BIOVALENTIA: Biological Research Journal
Yanti Yulianti
Unknown Affiliation
Agriculture, Biological Sciences & Forestry Arts Humanities Astronomy Biochemistry, Genetics & Molecular Biology Control & Systems Engineering Earth & Planetary Sciences Education Energy Environmental Science Immunology & microbiology Languange, Linguistic, Communication & Media Materials Science & Nanotechnology Mathematics Medicine & Pharmacology Physics

Published : 11 Documents Claim Missing Document
Claim Missing Document
Check
Articles

Found 11 Documents
Search

 1   2 
BEREBUT ´RUMAH TUHAN´ STUDI KASUS KONFLIK ANTARA JEMAAT GKJW DAN GPIB KELURAHAN CITRODIWANGSAN KECAMATAN LUMAJANG KABUPATEN LUMAJANG, 1975-1982 Yulianti, Yanti; Sasmita, Nurhadi; Badriyanto, Bambang Samsu
Publika Budaya Vol 1, No 1 (2013)
Publisher : Publika Budaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (177.043 KB)

Abstract

Artikel ini membahas tentang sejarah sosial dengan menggunakan konsep pendekatan sosiologi agama yang mempelajari peran agama dan peristiwa-peristiwa sosial dalam masyarakat Lumajang. Peristiwa-pristiwa sosial dapat memicu terjadinya konflik sehingga menimbulkan perubahan sosial di dalam masyarakat. Dengan menggunakan bahan-bahan teori sosiologi agama dan historis, artikel ini menyelidiki pandangan, pengetahuan, dan kepercayaan yang berhubungan, khususnya dengan konflik agama yang terjadi antara jemaat GKJW dengan GPIB Lumajang. Jika manusia sudah menjadi satu kesatuan dengan agama dan kelompoknya maka manusia tersebut berani membela agamanya yang dianggap benar sehingga cenderung berusaha menyelamatkan dan membela martabat agamanya. Seperti halnya yang terjadi di Lumajang kedua aliran gereja tersebut saling mempertahankan dan memperebutkan gerejanya, sehingga terjadi konflik. Mereka masing-masing mempunyai rasa ingin membela agama yang dianggapnya benar dan rela mempertahankan kekuasaan satu sama lain.
Analisis Termal-hidrolik Reaktor Cepat Berpendingin Gas (Gas Cooled Fast Reactor) Menggunakan Metode Runge Kutta Anggraini, Adeliya Ayu; Yulianti, Yanti; Manurung, Posman
Jurnal Teori dan Aplikasi Fisika Vol 6, No 2 (2018): Jurnal Teori dan Aplikasi Fisika
Publisher : Universitas Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jtaf.v6i2.1913

Abstract

The Research of Gas Cooled Fast Reactor (GCFR) thermal-hydraulics analysis has been done. This reseacrh aim to solve fuel rod heat conduction equation by Runge Kutta method and to get thermal-hydraulics parameters such as coolant axial temperature distribution, pressure drops, convection heat transfer coefficient, and fuel rod radial temperature distribution. Heat transfer of the reactors was assumted steady state (time independent) then obtained coolant inlet tempertaure about 450 oC, outlet temperature about 474,752 oC and convection heat transfer coefficient   about 2,5903 W/cm2 oC. Pressure drop by friction was 0,16968 bar, pressure drop by form was 0,31292 bar, pressure drop by gravity was 0,20580 bar and total pressure drop was 0,68838 bar. While centerline fuel obtained the maximum temperature of fuel rod about 2720,33812 oC and the lowest fuel rod temperature at cladding surface about 488,8205 oC.
THE ESSENTIAL CONTRIBUTION OF CAPTIVE SUMATRAN ELEPHANT IN ELEPHANT TRAINING CENTER, WAY KAMBAS NATIONAL PARK FOR WILDLIFE GENETICS CONSERVATION Rustiati, Elly Lestari; Priyambodo, Priyambodo; Yulianti, Yanti; Srihanto, Eko Agus; Pratiwi, Dian Neli; Virnarenata, Elsa; Novianasari, Tika; Krismuniarti, Elisabeth Devi; Saswiyanti, Enny
BIOVALENTIA: Biological Research Journal Vol. 6 No. 1 (2020)
Publisher : Biology Department, Faculty of Mathematics and Natural Sciences, Sriwijaya University

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1061.173 KB) | DOI: 10.24233/BIOV.6.1.2020.173

Abstract

Way Kambas National Park (WKNP) is home of five protected big mammals including sumatran elephants.  It shares its border with 22 of 37 villages surrounding the national park.  Understanding their existence in the wild is a priority, and  wildlife genetics is a crucially needed. Besides poaching and habitat fragmentation, wildlife-human conflict is one big issue.  Elephant Training Center (ETC) in WKNP is built for semi in-situ conservation effort on captive sumatran elephants that mainly have conflict histories with local people.  Participative observation and bio-molecular analysis were conducted to learn the importance of captive Sumatran elephant for conservation effort.  Through captive sumatran elephants, database and applicable methods are expected to be developed supporting the conservation of their population in the wild.  Participative observation and molecular identification was carried on captive sumatran elephants in ETC, WKNP under multiple year Terapan grant of Ministry of Research and Technology Higher Education, Indonesia. Gene sequence and cytological analyses showed that the captive sumatran elephants are closely related and tend to be domesticated.  Translocation among ETC to avoid inbreeding, and maintaining the captive sumatran elephant as natural as possible are highly recommended. Developing genetic database can be a reference for both captive and wild sumatran elephants.
Desain Reaktor Air Superkritis (Supercritical Cooled Water Reactor) dengan Menggunakan Bahan Bakar Uranium-horium Model Teras Silinder Sri Bawani; Yanti Yulianti
Jurnal Teori dan Aplikasi Fisika Vol 4, No 1 (2016): Jurnal Teori dan Aplikasi Fisika
Publisher : Universitas Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jtaf.v4i1.1313

Abstract

. Telah dilakukan penelitian desain reaktor air superkritis (SCWR) dengan bahan bakar uranium-thorium model teras silinder. Reaktor didesain untuk menghasilkan daya termal yang maksimal dan kondisi kritis. Parameter yang dianalisis adalah pengayaan bahan bakar fraksi volume, densitas atom, ukuran teras, kekritisan, dan distribusi rapat daya. Analisis reaktor dilakukan pada 1/6 bagian teras berbentuk silinder dua dimensi (x,y) menggunakan CITATION. Penelitian menggunakan bahan bakar U-235 dan Th-232, stainless steel sebagai selonsong, air ringan sebagai moderator dan pendingin. Diperoleh desain teras reaktor yang ideal dengan ukuran x = 340 cm dan y = 170 cm. Pengayaan pada bagian pertama bahan bakar 3,1704%, bagian kedua 2,5% dan bagian ketiga 4 %. Desain ini menghasilkan daya termal 1000 M Wth, rapat daya maksimal sebesar 114,4073 watt/cm3 dan nilai k-efektif sebesar 1,000006.
Desain Teras Reaktor High Temperatur Gas-Cooled Reactor (HTGR) Model Mesh Triangular Dua Dimensi Berbahan Bakar Thorium Berpendingin Gas CO2 Nasta Melia Dilaga; Yanti Yulianti; Agus Riyanto
Jurnal Teori dan Aplikasi Fisika Vol 7, No 1 (2019): Jurnal Teori dan Aplikasi Fisika
Publisher : Universitas Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jtaf.v7i1.1933

Abstract

The research of design reactor HTGR cell core with two dimensional triangular mesh model using thorium fueled and CO2 coolant has been done. Objective of the research was design critical condition of HTGR cell core so as obtained critical condition and high thermal power. The neutronic analyzed by CITATION of SRAC on 1/6 of reactor cell core. The parameter which analyzed were core fuel enrichment, size and configuration reactor cell core, critically and power density. The result was obtained the ideal reactor design with size (x) 202 cm and (y) 101 cm. The enrichment of first region was 3% and second region was 2.731%. The total thermal power of reactor was 100 MWth, maximum power density of reactor was 107.5371 Watt/cc and keff of reactor was 1.000008.
BEREBUT 'RUMAH TUHAN' STUDI KASUS KONFLIK ANTARA JEMAAT GKJW DAN GPIB KELURAHAN CITRODIWANGSAN KECAMATAN LUMAJANG KABUPATEN LUMAJANG, 1975-1982 Yanti Yulianti; Nurhadi Sasmita; Bambang Samsu Badriyanto
Publika Budaya Vol 1 No 1 (2013): November
Publisher : Fakultas Ilmu Budaya Universitas Jember

Show Abstract | Download Original | Original Source | Check in Google Scholar

Abstract

Artikel ini membahas tentang sejarah sosial dengan menggunakan konsep pendekatan sosiologi agama yang mempelajari peran agama dan peristiwa-peristiwa sosial dalam masyarakat Lumajang. Peristiwa-pristiwa sosial dapat memicu terjadinya konflik sehingga menimbulkan perubahan sosial di dalam masyarakat. Dengan menggunakan bahan-bahan teori sosiologi agama dan historis, artikel ini menyelidiki pandangan, pengetahuan, dan kepercayaan yang berhubungan, khususnya dengan konflik agama yang terjadi antara jemaat GKJW dengan GPIB Lumajang. Jika manusia sudah menjadi satu kesatuan dengan agama dan kelompoknya maka manusia tersebut berani membela agamanya yang dianggap benar sehingga cenderung berusaha menyelamatkan dan membela martabat agamanya. Seperti halnya yang terjadi di Lumajang kedua aliran gereja tersebut saling mempertahankan dan memperebutkan gerejanya, sehingga terjadi konflik. Mereka masing-masing mempunyai rasa ingin membela agama yang dianggapnya benar dan rela mempertahankan kekuasaan satu sama lain.
Design of Supercritical Water Reactor with Thorium Fuel Cell Rina Utami; Yanti Yulianti
Jurnal ILMU DASAR Vol 14 No 1 (2013)
Publisher : Fakultas Matematika dan Ilmu Pengetahuan Alam Universitas Jember

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (284.25 KB) | DOI: 10.19184/jid.v14i1.474

Abstract

The research of desain of super critical water reactor (SCWR) thorium fuel has been done. The objective of this research is to obtain the design with high thermal power and inherent safety features. The analyzed parameters were:corefuelenrichment,reactorsize,criticality,andpowerdensitydistribution.Acorecalculationof x,y,z was achieved by CITATION code. Fuel composition and core configurations in critical condition were calculated by variation of fuel enrichment, reactor size and configuration of the fuel in the core. SCWR used thorium as fuel, stainless steel as cladding, light water as moderator and coolant as well. This research obtained critical core design that is size x = 85 cm, y = 85 cm and z = 180 cm. The critical condition can be achieved when the inner fuel loaded about 2.23% fuel enrichment and outer fuel 1.5% fuel encrichmant. The design produced 1000 MW thermal power, the maximum power density is 625.675 Watts /cc and k-effective value is 1.000274. Thereactorcoreinthisresearchfulfillstheinherentsafetystandardintermofneutronicaspect. Keywords : Core design, SCWR, thorium, power density, passive safety
Perhitungan Burn Up pada Reaktor HCLWR Model Geometri Silinder 2 Dimensi Menggunakan Kode COREBN Siska Wulandari; Yanti Yulianti; Agus Riyanto
Jurnal Fisika Indonesia Vol 24, No 3 (2020)
Publisher : Department of Physics Universitas Gadjah Mada

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.22146/jfi.v24i3.57166

Abstract

Penelitian tentang perhitungan burn up pada reaktor HCLWR model geometri silinder 2 dimensi menggunakan kode COREBN telah dilakukan. Penelitian ini bertujuan untuk menghasilkan nilai rasio konversi lebih besar atau sama dengan 1 dan mempunyai nilai keffyang aman. Alat dan bahan yang digunakan yaitu seperangkat komputer dengan Operating System Linux Mint 18.1 dan SRAC-COREBN. Hal-hal yang dilakukan pada penelitian untuk memperoleh nilai rasio konversi dan keff yang diinginkan dengan cara memvariasikan persentase pengayaan, periode burn up, daya linear, dan mengubah fraksi volume material. Berdasarkan hasil penelitian dan analisis yang telah dilakukan, maka diperoleh nilai rasio konversi dan keff masing-masing sebesar 1,002300 dan 0,9011962. Desain reaktor yang menghasilkan nilai rasio konversi 1 dan keff kritis ketika persentase bahan bakar 42%, kelongsong 8%, dan moderator 50%; persentase di ketiga daerah bahan bakar masing-masing 2,5%; periode operasi reaktor 548 hari; daya reaktor 2600 MW; dan daya linear 1,943199 MW/cm.
Solusi Persamaan Difusi Neutron pada Pressurized Water Reactor (PWR) Berbentuk Silinder dengan Bahan Bakar Uranium Daur Ulang Riftaul Kurniawati; Yanti Yulianti; Iqbal Firdaus
Jurnal Teori dan Aplikasi Fisika Vol 11, No 2 (2023): Jurnal Teori dan Aplikasi Fisika
Publisher : Universitas Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jtaf.v11i2.6645

Abstract

The Research on solution of the neutron diffusion equation in a cylindrical Pressurized Water Reactor (PWR) with recycled uranium fuel. The research aims to obtain the distribution of neutron flux in a cylindrical Pressurized Water Reactor (PWR) using recycled uranium fuel. The method was carried out by means of simulations using the C++ programming language including determining the specifications of the reactor core, determining cell geometry and volume fraction, determining atomic density, calculating macroscopic cross-sections with the PIJ module, and calculating the neutron diffusion equation. After obtaining the solution of the neutron diffusion equation, calculations were carried out on ¼ part of the reactor core with a cylindrical cell geometry defined by IGT=3 on SRAC. The results obtained in this study are that the diffusion equation without a source of distribution of the highest neutron flux is in group 1 of 1.1681 × 10-10, the diffusion equation with a fission source of the highest distribution of neutron flux is in group 3 of 4.6009 × 10 -8, the diffusion equation with fission sources and the scattering distribution of the highest neutron flux is in group 3 with the division time of 1.1681 × 10-10, the diffusion equation with fission sources changes the power of 3,000 MW the highest distribution of neutron flux is in the group 3. The highest group has more neutron flux and changes in power do not affect the value of the neutron flux.
Solusi Persamaan Difusi Neutron Pada PWR (Pressurized Water Reactor) Berbentuk Heksagonal dengan Bahan Bakar Uranium Daur Ulang Risdha Ayu Shinta Dewi; Yanti Yulianti; Iqbal Firdaus
Jurnal Teori dan Aplikasi Fisika Vol 11, No 2 (2023): Jurnal Teori dan Aplikasi Fisika
Publisher : Universitas Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jtaf.v11i2.6646

Abstract

The Research on solution of the neutron diffusion equation with a PWR reactor using recycled uranium fuel at 1⁄6 section of the reactor core with a hexagonal IGT-6 geometry. The purpose of this research is to determine the distribution of the neutron flux in the PWR of recycled uranium fuel. The solution is done by computational simulation using the Dev-C++ programming. The parameters used in this study determine the specifications of the reactor core, determine the volume fraction, determine the atomic density, calculate the macroscopic cross-section with the PIJ module, calculate the neutron diffusion equation, calculate ϕ (x,y) using the Gauss Seidel method. The results obtained in this study are the neutron diffusion equation without a source obtaining the highest relative neutron flux value in group 1 of 4,5729×〖10〗^(-2), with a fission source obtaining the highest relative neutron flux value in group 3 of 7,3327×〖10〗^(-4), with fission and scattering sources obtaining the highest relative neutron flux value found in group 2 of 1,5157×〖10〗^(-3), and 3,200 MW of power is added to the source fission, the value of the neutron flux does not change. This is because the addition of power does not affect the value of the neutron flux.
Co-Authors Adi Saputra Agus Riyanto AGUS RIYANTO Anggraini, Adeliya Ayu Bambang Samsu Badriyanto Bambang Samsu Badriyanto Eko Agus Srihanto, Eko Agus Elly Lestari Rustiati Iqbal Firdaus Junaidi Junaidi Krismuniarti, Elisabeth Devi Marjunus, Roniyus Nasta Melia Dilaga Novianasari, Tika Nurhadi Sasmita Posman Manurung Pratiwi, Dian Neli Priyambodo Priyambodo Riftaul Kurniawati Rina Utami Risdha Ayu Shinta Dewi Saswiyanti, Enny Siska Wulandari Sri Bawani Sri Ratna Sulistiyanti Surtono, Arif Virnarenata, Elsa