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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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Journal : Jurnal Fisika FLUX

 1 
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.
Co-Authors Ali Djamhuri Evi Elisanti, Evi Hery Adrial, Hery Indra Hastuti, Indra Santoso, Aris Priyo Agus Zuhair Zuhair