Results 11 to 20 of about 203,006 (296)
Behavior of High Burn-up Fuel Cladding under LOCA Conditions [PDF]
Journal of Nuclear Science and Technology, 2009 LOCA-simulated experiments were performed with MDA, ZIRLO™, M5®, NDA, and Zircaloy-2 cladding specimens with local burn-ups ranging from 66 to 76 MWd/kg. Short test rods fabricated with the cladding specimens were heated, isothermally oxidized at 1,459 to 1,480K in steam flow, and finally quenched in flooding water.
Fumihisa NAGASE +2 more
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Microhardness and Young's modulus of high burn-up UO2 fuel
Journal of Nuclear Materials, 2016 AbstractVickers microhardness (HV0.1) and Young's modulus (E) measurements of LWR UO2 fuel at burn-up ≥60 GWd/tHM are presented. Their ratio HV0.1/E was found constant in the range 60–110 GWd/tHM. From the ratio and the microhardness values vs porosity, the Young's modulus dependence on porosity was derived and extended to the full radial profile ...
Cappia, F. +8 more
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FUEL BURN-UP CALCULATION FOR WORKING CORE OF THE RSG-GAS RESEARCH REACTOR AT BATAN SERPONG
Jurnal Penelitian Fisika dan Aplikasinya, 2017 The neutronic parameters are required in the safety analysis of the RSG-GAS research reactor. The RSG-GAS research reactor, MTR (Material Testing Reactor) type is used for research and also in radioisotope production.
Tukiran Surbakti, Mochammad Imron
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Analisis Burn Up pada Reaktor Cepat Berpendingin Gas Menggunakan Bahan Bakar Uranium Alam
JIF (Jurnal Ilmu Fisika), 2015 Burn up analysis of gas cooled fast reactor (GCFR) with natural uranium fuel has been done. Burn up modification used in order to make reactor can be operated with natural uranium without enrichment.
Feriska Handayani Irka +1 more
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The high burn-up structure in nuclear fuel
Materials Today, 2010 During its operating life in the core of a nuclear reactor nuclear fuel is subjected to significant restructuring processes determined by neutron irradiation directly through nuclear reactions and indirectly through the thermo-mechanical conditions established as a consequence of such reactions.
Rondinella, Vincenzo V., Wiss, Thierry
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DISCUSSION ABOUT HBS TRANSFORMATION IN HIGH BURN-UP FUELS [PDF]
Nuclear Engineering and Technology, 2009 High burn-up transformation process in low temperature nuclear fuel oxides material was observed in the early sixties in LWR UO 2 fuels, but not studied in depth. Increasing progressively the fuel discharge burn-up in PWR power plants, this material transformation was again observed in 1985 and identified as an important process to be accounted for in
Daniel Baron +3 more
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Automated system for determining the burnup of spent nuclear fuel
Tekhnologiya i Konstruirovanie v Elektronnoi Apparature, 2014 The authors analyse their experience in application of semiconductor detectors and development of a breadboard model of the monitoring system for spent nuclear fuel (SNF). Such system should use CdZnTe-detectors in which one-charging gathering conditions
V. A. Mokritskii +2 more
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Shielding Design and Dose Evaluation for HTR-PM Fuel Transport Pipelines by QAD-CGA Program
Science and Technology of Nuclear Installations, 2021 The spherical fuel elements are adopted in the high-temperature gas-cooled reactor pebble-module (HTR-PM). The fuel elements will be discharged continuously from the reactor core and transported into the fuel transport pipelines during the reactor ...
Sheng Fang +6 more
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Use of erbium as a burnable absorber for the VVER reactor core life extension [PDF]
Nuclear Energy and Technology, 2020 The paper presents the results of a computational and theoretical analysis concerned with the use of erbium as a burnable absorber in VVER-type reactors.
Saleh H. Alassaf +2 more
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Crystal Structure of the ZrO Phase at Zirconium/Zirconium Oxide Interfaces [PDF]
, 2014 Zirconium-based alloys are used in water-cooled nuclear reactors for both nuclear fuel cladding and structural components. Under this harsh environment, the main factor limiting the service life of zirconium cladding, and hence fuel burn-up efficiency ...
Grovenor, CRM +8 more
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