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All Journal Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir Jurnal Fisika FLUX Al-Manhaj: Jurnal Hukum dan Pranata Sosial Islam
Suwoto Suwoto
Pusat Teknologi Reaktor dan Keselamatan Nuklir (PTRKN) - BATAN
Religion Humanities Earth & Planetary Sciences Economics, Econometrics & Finance Education Law, Crime, Criminology & Criminal Justice Materials Science & Nanotechnology Physics

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STUDI DAN KAJIAN DATA NUKLIR REAKTOR GENERASI-IV DENGAN SPEKTRUM NEUTRON CEPAT Suwoto, Suwoto; Zuhair, Zuhair
Jurnal Fisika FLUX Vol 10, No 1 (2013): Jurnal Fisika FLUX Edisi Februari 2013
Publisher : Lambung Mangkurat University Press

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.20527/flux.v10i1.2633

Abstract

Abstract. STUDY AND ASSESSMENT OF GENERATION IV REACTOR NUCLEARDATA WITH FAST NEUTRON SPECTRA. Generation IV International Forum (GIF)has evaluated and assessed NES of Gen- IV and selected six potential types ofreactors to be deployed in the next decade. Those include GFR, LFR, SFR, MSR,SCWR and VHTR. The first three reactors were fast neutron spectrum applied and therest reactors were thermal neutron spectrum used. The study and assessment focusedon the nuclear data characteristic parameter and nuclear data uncertainties of Gen-IVreactor with fast neutron spectrum. Until 2008, the accuracy target of nuclear datacross-sections used it in fast reactor spectrum calculation are relatively significantespecially for σ-capture, σ-fission, and σ-inelastic. Several differences of nuclear datacross-sections on minor actinide isotopes between expected and targeted parametersare observed such as σ-fission of Cm-244 isotope up to 10 times larger and σ-captureof 92-U-238 isotope around 1.5-2 times higher than targeted parameters. Uncertaintyand accuracy of minor actinide cross-sections for fast spectrum Gen-IV reactorsprovide relatively significant discrepancies (1.3 to 10 times higher) in term of accuracybetween expected and targeted parameters. Some differences of provided results fromany experimental and assessment data with several evaluated nuclear data files for Pbare found. Some discrepancies on integral parameter of fast spectrum Gen-IV reactorsbetween expected and targeted such keff, void reactivity and Doppler effects, peakpower and burn-up are clearly observed. Accurate and precise cross-sections data ofradiation captured and threshold reaction cross sections such as (n,2n), (n,3n), (n,p),(n,α) are necessary for fast reactors.Keywords: cross-sections, fast neutron spectrum, GFR, LFR, SFR, uncertainty, targetaccuracy
Analisis Perhitungan Benchmark Keselamatan Kritikalitas Larutan Uranil Nitrat di Teras Slab 280T STACY Zuhair, Zuhair; Suwoto, Suwoto; Suharno, Suharno
Jurnal Fisika FLUX Vol 8, No 2 (2011): Jurnal Fisika Flux Edisi Agustus 2011
Publisher : Lambung Mangkurat University Press

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.20527/flux.v8i2.3115

Abstract

Criticality benchmark experiment at STACY critical facility is important forvalidation of computation technique and nuclear data library used in design of nuclearfuel cycle criticality safety. This paper discusses criticality safety benchmarkcalculation at STACY facility, which uses uranyl nitrate solution with MCNP-4C MonteCarlo transport code. The continuous energy nuclear data library was utilized inbenchmark calculation to complete criticality safety analysis. The MCNP-4C criticality(keff) prediction indicated overestimated results for all configurations except forconfiguration 131. The biases of calculation with criticality experiment (keff = 1) wereunder 0.26%. Configuration 140 calculation showed the most precisely agreement withC/E value of 1.0001. From these results, it can be concluded that the capability andreliability of MCNP-4C is constantly high in prediction of criticality accuracy for uranylnitrate solution at STACY 280T slab core.
Analisis Yuridis Alih Fungsi Tanah Kas Desa Untuk Pembangunan Kolam Renang di Desa Udanwuh Suwoto, Suwoto; Santoso, Aris Priyo Agus; Hastuti, Indra; Elisanti, Evi
AL-MANHAJ: Jurnal Hukum dan Pranata Sosial Islam Vol 5 No 2 (2023)
Publisher : Fakultas Syariah INSURI Ponorogo

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.37680/almanhaj.v5i2.3354

Abstract

The aim of this research is to determine the regulation of the transfer of land to the village treasury and the obstacles of the Udanwuh Village government to building a swimming pool. The research location is at the Udanuwuh Village Hall Office, Kaliwungu District, Semarang Regency. The type of research used is an empirical juridical approach. The type of data, namely primary data, was obtained through interviews and discussions with several parties in order to provide information related to the transfer of land to the village treasury. Secondary data was obtained from library literature. Data collection techniques through literature study, interviews. Qualitative descriptive data analysis techniques. The results of the research show that the arrangement for the conversion of Village treasury land for the construction of a swimming pool in Udanwuh Village is in the form of government land in Udanwuh Village on title C Village Number 4, Plot 29 Class SII located in Ngrancah Hamlet RT.03 RW.02 village treasury land with a total area of + /- 833m2 and for the construction of swimming pools of +/-753 m2 and +/-130 m PDAM is used. Obstacles related to licensing for the conversion of village treasury land for the construction of swimming pools are based on Semarang Regency Regional Regulation No. 14 of 2003. However, with the issuance of Regional Regulation No. 21 of 2021 concerning the revocation of Semarang Regency Regional Regulation No. 14 of 2003, this has resulted in permits not being completed or delayed. The conclusion of the research is that the conversion of land functions in order to comply with applicable regulations, has a positive impact on the progress of the village, optimal management of land conversion, maximum utilization of the function of the Village treasury land into a swimming pool to improve the village economy and village community, resolving solutions to problems in make regulations regarding the transfer of cash land functions in the construction of swimming pools.
Analisis Kuat Sumber Neutron Dan Perhitungan Laju Dosis Neutron Teras Awal RDE Suwoto, Suwoto; Adrial, Hery; Zuhair, Zuhair
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 23, No 1 (2017): Februari 2017
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (487.916 KB) | DOI: 10.17146/urania.2017.23.1.3119

Abstract

Teras reaktor RDE (Reaktor Daya Eksperimental) berbentuk silinder non anular, mengadopsi teknologi HTGR (High Temperature Gas-cooled Reactor) berbahan bakar kernel partikel berlapis TRISO dalam bentuk bola (pebble) dan berpendingin gas helium. Desain teras reaktor RDE ini mengadopsi teknologi reaktor temperatur tinggi HTGR dengan keselamatan inherent pasif yang sangat aman. Temperatur keluaran panas gas helium teras reaktor RDE dirancang pada kisaran 700°C dengan temperatur masukan sekitar 250°C. Di samping menghasilkan listrik, reaktor RDE didisain menghasilkan panas temperatur tinggi yang dapat digunakan untuk keperluan kogenerasi lainnya (penelitian panas proses lainnya). Bahan bakar pada RDE berbentuk bola yang berisikan kernel partikel berlapis TRISO yang berupa uranium oksida (UO2) berpengkayaan 17%. Lapisan TRISO terdiri 4 lapisan yaitu lapisan karbon penyangga berpori, lapisan karbon pirolitik bagian dalam (IPyC, Inner Pyrolitic Carbon), lapisan Silikon Karbida (SiC) dan lapisan pirolitik karbon bagian luar (OPyC, OuterPyrolitic Carbon). Analisis kuat sumber dan perhitungan awal laju dosis neutron pada teras RDE dilakukan menggunakan program Monte Carlo MCNP5v1.2. Pemodelan heterogenitas ganda pada bahan bakar kernel partikel berlapis TRISO dan pada bahan bakar bola pada teras RDE. Dengan memanfaatkan program EGS99304, jumlah struktur group energi yaitu 640 (SAND-II group structure) digunakan dalam perhitungan spektrum neutron pada reaktor RDE. Teras reaktor RDE dibagi dalam 100 zona (10 arah radial dan 10 arah aksial). Analisis hasil perhitungan menunjukkan bahwa kuat sumber neutron reaktor RDE sebesar 8,47027X1017 neutron/sekon. Distribusi laju dosis neutron ditentukan menggunakan faktor konversi fluks ke dosis neurton dari International Commission on Radiological Protection, ICRP dan NCRP. Hasil perhitungan awal laju dosis neutron dengan faktor konversi ICRP-21 dan NCRP-38 untuk pekerja radiasi pada arah radial di perisai biologis sudah melemah memberikan nilai masing-masing sebesar 6,69915 µSv/jam dan 6,9964 µSv/jam pada posisi 215 cm dari pusat teras RDE, sehingga pekerja radiasi aman dan terlindungi dari radiasi sesuai dengan persyaratan Perka Bapeten  No. 04 tahun 2013 tentang Proteksi dan Keselamatan Radiasi Dalam Pemanfaatan Tenaga Nuklir yang menetapkan nilai batas dosis efektif rerata untuk pekerja radiasi adalah 20 mSv/tahun (10 µSv/jam). Dari hasil analisis tersebut tampak bahwa model perisai radiasi dan perisai biologis telah memenuhi standar keselamatan radiasi yang disyaratkan.Kata kunci: TRISO, Pebble, MCNP5v1.2, RDE, kuat sumber neutron, laju dosis neutron, ICRP, NCRP
Co-Authors Ali Djamhuri Evi Elisanti, Evi Hery Adrial, Hery Indra Hastuti, Indra Santoso, Aris Priyo Agus Zuhair Zuhair