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All Journal Abdi Laksana : Jurnal Pengabdian Kepada Masyarakat International Journal of Scientific Multidisciplinary Research (IJSMR) Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Suwoto
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Decision Sciences, Operations Research & Management Economics, Econometrics & Finance Education Law, Crime, Criminology & Criminal Justice Mechanical Engineering Social Sciences Other

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Evaluation of Public Services through the "Lapor Pak Yes" Program at the Communication and Informatics Office of Lamongan Regency Suwoto; Ika Devy Pramudiana; Sri Kamariyah; Zainal Fatah
International Journal of Scientific Multidisciplinary Research Vol. 2 No. 12 (2024): December 2024
Publisher : PT FORMOSA CENDEKIA GLOBAL

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55927/ijsmr.v2i12.13064

Abstract

This study aims to evaluate the implementation of the "Lapor Pak Yes" program initiated by the Communication and Information Technology Office of Lamongan Regency as an innovation in public service. The program is designed to accelerate the resolution of public complaints through various communication channels, such as WhatsApp, Instagram, Telegram, and the national platform SP4N-LAPOR!. This research utilizes Dunn's (2003) policy evaluation theory, which includes six main criteria: effectiveness, efficiency, adequacy, equity, responsiveness, and appropriateness. A qualitative approach was employed in this study, with data collection techniques including in-depth interviews, observations, and document analysis. The study involves various stakeholders, including local government officials and community members who actively use the "Lapor Pak Yes" program. The data collected highlights findings regarding the program's effectiveness in addressing public complaints, the challenges faced, and its impact on improving the quality of public services. The findings reveal that although the number of complaints received was relatively high, with approximately 319 reports related to civil services in 2022, the rate of complaint resolution remains low. Around 40% of reports concerning infrastructure issues, such as road repairs and flood management, were not promptly addressed
Penyuluhan Dan Pelatihan Pembuatan Sabun Transparan Suwoto; Indrawijaya, Budhi; Wibisana, Ahmad
Abdi Laksana : Jurnal Pengabdian Kepada Masyarakat Vol 5 No 1 (2024): Abdi Laksana : Jurnal Pengabdian Kepada Masyarakat
Publisher : LPPM Universitas Pamulang

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.32493/abdilaksana.v5i1.38485

Abstract

Telah dilakukan kegiatan PKM berupa penyuluhan dan pelatihan pembuatan sabun transparan. Kegiatan dilakukan di RW 019 Perumahan Villa Pamulang Pondok Benda Pamulang. Sabun merupakan kebutuhan pokok yang dibutuhkan untuk menjaga kebersihan dan kesehatan. Selama ini sabun diperoleh masyarakat dari membeli produk yang sudah ada dan merupakan bagian dari kebutuhan pokok mereka. Dengan semakin meningkatnya pengetahuan dan kesadaran masyarakat akan pentingnya menjaga kesehatan, kebutuhan akan sabun mandi dengan kondisi tertentu seperti herbal dengan berbagai manfaat tambahan dan juga tampilan yang transparan dan menarik makin dibutuhkan masyarakat.Pembuatan sabun ini cukup mudah dilakukan oleh masyarakat awam tanpa menggunakan peralatan khusus, namun diperlukan pengetahuan tentang sabun dan bahan lain terkait serta potensi bahaya yang dapat ditimbulkan. Pada pelatihan pkm ini diajarkan cara pembuatan sabun. Pelatihan dilakukan berupa penjelasan oleh dosen dan dilakukan praktek langsung oleh mahasiswa di depan para peserta. Pelatihan berlangsung lancar dan mendapat sambutan yang sangat baik dari masyarakat. Para peserta berharap agar kegiatan PKM dapat dilakukan secara berkesinambungan sehingga masyarakat dapat menerapkan pelatihan ini dalam pengembangan kewirausahaan dan dapat menunjang ekonomi masyarakat.
EFFECTS OF FUEL DENSITY ON REACTIVITY COEFFICIENTS AND KINETIC PARAMETERS OF PEBBLE BED REACTOR Suwoto; R. Andika Putra Dwijayanto; Wahid Luthfi; Zuhair
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 28 No. 1 (2022): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2022.28.1.6625

Abstract

Few decades ago, a large number of nuclear reactors were designed to use HEU as the fuel. But the use of HEU is being discouraged since it can be used as a nuclear explosive material which makes its proliferation potential. Most of the HEU-fueled nuclear reactors in the world are either closed or converted into other types that have LEU fuel with 235U enrichment below 20%. To extend lifetime, LEU fuel with high density is developed. The change in fuel density from low to high will also change core neutronics and thermal hydraulics of the reactor, and as a result, it affects the transient response of the reactor. This paper studies the effects of fuel density on reactivity coefficients and kinetic parameters of pebble bed reactor through several calculations with MCNP6 code combine with ENDF/B-VII.1 continuous energy cross-section nuclear data library. The overall calculation results show that the Doppler temperature coefficient (DTC) increases with increasing fuel density, but the moderator temperature coefficient (MTC) decreases due to hardening of neutron spectrum. Kinetic parameters such as effective delayed neutron fraction (βeff), prompt neutron lifetime(ℓ) and neutron generation time (Ʌ) which significantly reduced with increasing fuel density will strongly affect the reactor control and safety. The results of this work conclude that the selection of 9–15 g/cm3 fuel density should be considered carefully given that its effect on reactor controllability.
STUDY ON CRITICALITY AND NEUTRONIC SAFETY PARAMETERS OF NUSCALE FUEL ASSEMBLY Zuhair; Wahid Luthfi; R. Andika Putra Dwijayanto; Suwoto
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 3 (2021): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.3.6509

Abstract

NuScale, a typical Pressurized Water Reactor (PWR) Small Modular Reactors (SMRs), offers a new opportunity for the future of nuclear industry. With 160 MW thermal power, NuScale has several advantages such as flexibility due to its modularity in construction. This work is focused on the study of criticality and neutronic safety parameters of NuScale fuel assembly using MCNP6 code and ENDF/B-VII library. The calculation results shows that criticality of fuel assembly type D is the highest among other assembly types because it has a fuel pin with pure UO2 without Gd2O3 concentration. The Doppler temperature coefficient (DTC) of fuel assembly type C is the most negative among other assemblies due to Doppler broadening effect on resonance region of capture cross section of 238U which is the highest concentration. The moderator temperature coefficient (MTC) of fuel assembly type D is the most negative among the other assembly types. The effective delayed neutron fraction (βeff) does not reflect a consistent trend among fuel assembly types. Fuel assembly type D shows the highest prompt neutron lifetime (ℓ) while the highest neutron generation time (Ʌ) is shown in assembly type C. It can be concluded that this study provides adequate results that can be used as a first step to carry out the neutronic computation and analysis of the NuScale full core.
ANALISIS KUAT SUMBER NEUTRON DAN PERHITUNGAN LAJU DOSIS NEUTRON TERAS AWAL RDE Suwoto; Hery Adrial; Zuhair
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 1 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2017.23.1.3119

Abstract

The reactor core RDE (Experimental Power Reactor) has non-annular cylindrical shape with coated fuel particles TRISO kernel in the spherical form (pebble) and cooled by helium gas. The RDE reactor core design is very safe, because it adopts the high-temperature reactor technology (HTGR) with inherent passive safety. The designed input helium temperature of RDE core is about 250 °C and the output of helium gas temperature helium of the reactor core of 700 °C. Beside of generating electricity, the RDE reactor is designed to generate high temperature gas that can be used for any purposes such as cogeneration (heat process application research). The spherical fuel called as pebble containing thousand of kernel TRISO-coated fuel particles of uranium dioxide 17 % (235U) enriched. TRISO coating comprises four layers, namely: porous carbon buffer layer, inner part pyrolytic carbon layer (IPyC, Inner Pyrolitic Carbon), silicon carbide layer (SiC) and a layer of pyrolytic carbon outer part (OPyC, Outer Pyrolitic Carbon). Analysis of neutron source strength and preliminary calculation of neutron dose rate on the RDE core were performed using Monte Carlo MCNP5v1.2 code. Double heterogeneity treatment in TRISO-coated fuel particles kernel and the pebble of the core are applied. Utilization of EGS99304 code to determine 640 amount of energy group structures (SAND-II neutron group structures) are used in the neutron spectrum calculation in the reactor. The reactor core is divided into 100 zones (10 in radial and 10 in axial directions). An analyses calculation result shows that the neutron source strength of the core is about 8.47027X1017neutron/sec. The neutron dose rate distributions are determined using a conversion factor of flux-to-dose taken from International Commission on Radiological Protection (ICRP) and National Council on Radiation Protection and Measurements (NCRP). The preliminary calculations result of neutrons dose rate using ICRP-21 and NCRP-38 conversion factor for radiation workers in the radial direction in the shield biological are already weakened as low as 6.69915 and 6.9964 μSv/h, respectively, at a position of 215 cm from the center part of the core. This result analysis indicate that radiation workers are safe and protected from neutron radiation sources in accordance with the regulatory requirements. Overall, from the calculation and analysis, it appears that the radiation and biological shielding model meets to the standards of radiation safety required. The results of this study can be used to complete the design data thickness of shielding of the reactor.
Co-Authors Ahmad Wibisana, Ahmad Hery Adrial Ika Devy Pramudiana Indrawijaya, Budhi R. Andika Putra Dwijayanto Sri Kamariyah Wahid Luthfi Zainal Fatah Zuhair