Providensia Allah di masa Pandemi Covid-19

Adapun tujuan dari penelitian tentang ‘providensia Allah di masa Pandemi’ adalah untuk mengingatkan serta menguatkan orang percaya secara khusus, untuk tetap berdiri teguh pada Yesus Kristus yang adalah batu karang yang teguh itu. Dengan demikian, orang percaya diharapkan tetap beriman pada pemeliharaan Allah, sekalipun di masa sulit akibat Pandemi. Adapun metode penelitian yang digunakan adalah kualitatif deskriptif, dengan sistem pengumpulan data library research melalui bantuan buku-buku serta artikel jurnal yang terkait. Dalam penelitian ini, ditemukan fakta bahwa sekalipun manusia tidak setia, Allah tetap setia untuk menjaga dan memelihara ciptaan. Lebih dari itu, Allah melalui sejarah menunjukkan kedaulatan-Nya atas alam semesta, yakni melalui pra-pengetahuan-Nya atas segala sesuatu dan menjadikan segala sesuatu untuk tujuan kekal-Nya.

Activities in Divertor Reflector and Linear Plates Using WCLL and HCPB Breeding Blanket Concepts

In fusion devices, such as European Demonstration Fusion Power Reactor (EU DEMO), primary neutrons can cause material activation due to the interaction between the source particles and the targeting material. Subsequently, the reactor’s inner components become activated. For safety and safe performance purposes, it is necessary to evaluate neutron-induced activities. Activities results from divertor reflector and liner plates are presented in this work. The purpose of liner shielding plates is to protect the vacuum vessel and magnet coils from neutrons. As for reflector plates, the function is to shield the cooling components under plasma-facing components from alpha particles, thermal effects, and impurities. Plates are made of Eurofer with a 3 mm layer of tungsten, while the water is used for cooling purposes. The calculations were performed using two EU DEMO MCNP (Monte Carlo N-Particles) models with different breeding blanket configurations: helium-cooled pebble bed (HCPB) and water-cooled lithium lead (WCLL). The TENDL–2017 nuclear data library has been used for activation reactions cross-sections and nuclear reactions. Activation calculations were performed using the FISPACT-II code at the end of irradiation for cooling times of 0 s–1000 years. Radionuclide analysis of divertor liner and reflector plates is also presented in this paper. The main radionuclides, with at least 1% contribution to the total value of activation characteristics, were identified for the previously mentioned cooling times.

SISTEM INFORMASI TATA KELOLA PERPUSTAKAAN BERBASIS WEB PADA DINAS KEARSIPAN DAN PERPUSTAKAAN PROVINSI GORONTALO

The research aims to facilitate the process of processing library data in the form of database storage, resulting in accurate reports, in pandemic times where all employees are required to do their duties from home so that staff in the field of services and technology, staffing, and governance have difficulty processing library data. Although it has used a computer as a means of support, the processing of data libraries is still stored using Ms.office, resulting in ineffectiveness in the work. The application of the information system has helped employees in accelerating the creation and submission of reports carried out in the Ministry of Archives and Library of Gorontalo Province using descriptive methods. The number of visitors who come on average is 51 people/day, and for the month as many as1,224 people. So the total number of visitors in 2020 is 14,688 people.Web-Based Library Governance Information System at the Ministry of Archives and Library of Gorontalo Province can provide convenience in processing Data Library and assist employees in doing their work from home (WFH)

Preliminary Neutronic Analysis of 150 MWt High-Temperature Gas Reactor to Produced Electricity in Small Area

There are small areas in Indonesia with insufficient electricity. High-Temperature Gas Reactor (HTGR) is a promising nuclear power plant that can be used in such areas as its capability to produce electricity and co-generation applications. A preliminary study on the neutronic aspect of the 150 MWt HTGR design is performed in this research. High Temperature Engineering Test Reactor (HTTR) is used as a basic model. The calculation was performed by Standard Thermal Reactor Analysis Code (SRAC) code, and Japanese Evaluated Nuclear Data Library (JENDL) 4.0 as nuclear data library. As a result, by increasing HTTR fuel assembly geometry to 1.5 times its original and using higher uranium enrichment, the reactor can be operated for five years.

Neutronics performances of gas-cooled fast reactor for 300-600 MWt Output Power with Modified CANDLE burn-up scheme in radial direction

Gas-Cooled Fast Reactor-GFR is a Generation IV reactor that is helium-cooled and has a closed fuel cycle. Due to the target operation on 2022-2030, this reactor type still needs further research and development technologies. We investigated the neutronics performances of a GFR balance type core with some modification of CANDLE (Constant Axial shape of Neutron flux, nuclide densities and power shape During Life of Energy production) burn-up scheme in the radial direction. The output power varied from 300 to 600 MWt. The neutronics calculation was performed using SRAC 2002 with JENDL 4.0 nuclear data library. The analysis indicate the reactor could operate critically for ten years without refueling with burn-up level 20% HM.

Impact of Different Nuclear Data Library on Control Rod Reactivity Worth Calculation of Small Pebble Bed Reactor

One of the main critical issues on a nuclear reactor is safety and control system. The control rod worth plays an important role in the safety and control of nuclear reactors. The control rods worth calculation is used to specify the safety margin of the reactor. The main objective of this work is to investigate impact of different nuclear data libraries on calculating the control rod reactivity worth on small pebble bed reactor. Calculation of the control rod reactivity worth in small high temperature gas cooled reactor has been conducted using the Monte Carlo N-Particle 6 (MCNP6) code coupled with a different nuclear data library. Famous evaluated nuclear data libraries such as JENDL-40u, ENDF/B-VII.1 and JEFF-3.2 continuous cross section-energy data libraries were used. The overall calculation results of integral control rod worth show that the ENDF/B-VII.1, JENDL-40u and JEFF-3.2 files give values of - 17.814%☐k/k, -18.0204 %☐k/k and -18.0267%☐k/k, respectively. Calculations using ENDF/B-VII.1 give a slightly lower value than the others, while the JENDL-4.0u file gives results that are close to JEFF-3.2 file. The different nuclear data libraries have a relatively small impact on the control rod worth of small pebble bed reactor. Accurate prediction by simulation of control rod worth is very important for the safety operation of all reactor types, especially for new reactor designs.