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Showing posts with label Generation IV Reactor. Show all posts
Showing posts with label Generation IV Reactor. Show all posts

Tuesday, August 17, 2010

Study And Assessment Of Generation IV Reactor Nuclear Data With Fast Neutron Spectra

STUDY AND ASSESSMENT OF GENERATION IV REACTOR NUCLEAR DATA WITH FAST NEUTRON SPECTRA

Suwoto
PTRKN-BATAN, Kawasan PUSPIPTEK Gd. 80, Serpong, Tangerang, 15310


ABSTRACT
STUDY AND ASSESSMENT OF GENERATION IV REACTOR NUCLEAR DATA WITH FAST NEUTRON SPECTRA.
Generation IV International Forum (GIF) has evaluated and assessed NES of Gen-IV and selected six potential types of reactors to be deployed in the next decade. Those include GFR, LFR, SFR, MSR, SCWR and VHTR. The assessment focused on the nuclear data characteristic parameter and nuclear data uncertainties of Gen-IV reactor with fast neutron spectrum. Until 2008, the accuracy target of nuclear data cross-sections used it in fast reactor spectrum calculation are relatively significant especially for s-capture, s-fission, and s-inelastic. Several differences of nuclear data cross-sections on minor actinide isotopes between expected and targeted parameters are observed such as sfission of Cm-244 isotope up to 10 times larger and s-capture of 92-U-238 isotope around 1.5-2 times higher than targeted parameters. Uncertainty and accuracy of minor actinide cross-sections for fast spectrum Gen-IV reactors provide relatively significant discrepancies (1.3 to 10 times higher) in term of accuracy between expected and targeted parameters. There are some differences of several evaluated nuclear data files. Some discrepancies on integral parameter of fast spectrum Gen-IV reactors between expected and targeted such k-eff, void reactivity and Doppler effects, peak power and burn-up are clearly observed. Accurate and precise cross-sections data of radiation captured and threshold reaction cross sections such as (n,2n), (n,3n), (n,p), (n,a) are necessary for fast reactors.

Keywords: cross-sections, fast neutron spectrum, GFR, LFR, SFR, uncertainty and target accuracy
Published : Proceeding "SEMINAR NASIONAL PENGEMBANGAN ENERGI NUKLIR II 2009", Jakarta, 25 Juni 2009.

Wednesday, December 30, 2009

Assessment Of Generation IV Reactors Secondary System For Hydrogen Production

ASSESSMENT OF GENERATION IV REACTORS SECONDARY SYSTEM FOR HYDROGEN PRODUCTION

Ign. Djoko Irianto
Center for Reactor Technology and Nuclear Safety � BATAN
Kompleks Puspiptek Serpong, Tangerang Selatan

ABSTRACT
ASSESSMENT OF GENERATION IV REACTORS SECONDARY SYSTEM FOR HYDROGEN PRODUCTION.
Nuclear power plans (NPP) is one of electrical generation plans which are environmental friendly. It means that NPP does not release exhaust gases contaminating environment. Continuous and increasing demand of clean energy quantitatively triggers the development of the next generation of nuclear energy systems (NES), which have to fulfill several criteria, such as economic, sustainable, safe and reliable, proliferation resistant and have physical protection concept. Nowadays, Generation IV Nuclear Energy Systems consist of Gas-cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), Sodium-cooled Fast Reactor (SFR), Super-Critical-cooled Water Reactor (SCWR), and Very High Temperature Reactor (VHTR). The application of the next generation of nuclear reactor designs or Generation IV reactors has been diversified including electricity and non-electricity. One of non electricity applications is the use of nuclear power plant for hydrogen production. There are three methods underlying the hydrogen production processes : water electrolysis, steam reforming of methane, and sulfur-iodine cycle. Parameters of efficiency, outlet temperature of secondary system, and other characteristics of secondary system make the combination of VHTR and steam reforming of methane process or VHTR and sulfur-iodine cycle process become good alternative for hydrogen production installation.
Keywords : Gen.IV Reactors, Secondary System, Hydrogen Production, VHTR, .
Published : 2007, Technical Report, Proceeding "PRESENTASI ILMIAH TEKNOLOGI KESELAMATAN NUKLIR XIII", ISSN No. : 1410-0533

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