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Nuclear Technology Volume 120, 1997 - Issue 1
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Technical Paper

Determination of Code Accuracy in Predicting Small-Break LOCA Experiment

Borut MavkoJožef Stefan Institute Jamova 39, 1000 Ljubljana, Sloveni
,
Andrej ProšekJožef Stefan Institute Jamova 39, 1000 Ljubljana, Sloveni
&
Francesco D’auriaUniversity of Pisa, Via Diotisalvi 2, 56126 Pisa, Italy
Pages 1-18 | Published online: 12 May 2017

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Read on this site (4)

Francesco D’Auria, José Luis Gago Moreno, Giorgio Maria Galassi, Davor Grgic & Antonino Spadoni. (2003) Three Mile Island Unit 1 Main Steam Line Break Three-Dimensional Neutronics/Thermal-Hydraulics Analysis: Application of Different Coupled Codes. Nuclear Technology 142:2, pages 180-204.
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Francesco D’Auria & Walter Giannotti. (2000) Development of a Code with the Capability of Internal Assessment of Uncertainty. Nuclear Technology 131:2, pages 159-196.
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Andrej Prosek & Borut Mavko. (1999) Evaluating Code Uncertainty–II: An Optimal Statistical Estimator Method to Evaluate the Uncertainties of Calculated Time Trends. Nuclear Technology 126:2, pages 186-195.
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Andrej Prosek & Borut Mavko. (1999) Evaluating Code Uncertainty—I: Using the CSAU Method for Uncertainty Analysis of a Two-Loop PWR SBLOCA. Nuclear Technology 126:2, pages 170-185.
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Articles from other publishers (8)

Hong Xu, Aurelian Florin Badea & Xu Cheng. (2022) Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark. Journal of Nuclear Engineering and Radiation Science 8:2.
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F.D’Auria, O. Mazzantini & G.M. Galassi. 2022. Pressurized Heavy Water Reactors. Pressurized Heavy Water Reactors 205 547 .
F. D’Auria, G.M. Galassi & O. Mazzantini. 2022. Pressurized Heavy Water Reactors. Pressurized Heavy Water Reactors 51 204 .
Tamás Varju, Ádám Aranyosy, Róbert Orosz, Viktor Holl, Tamás Hajas & Attila Aszódi. (2021) Analysis of the IAEA SPE-4 small-break LOCA experiment with RELAP5, TRACE and APROS system codes. Nuclear Engineering and Design 377, pages 111109.
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Gy. Ézsöl, L. Perneczky, L. Szabados & I. Tóth. (2012) PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Power Plants. Science and Technology of Nuclear Installations 2012, pages 1-22.
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Andrej Prošek, Matjaž Leskovar & Borut Mavko. (2008) Quantitative assessment with improved fast Fourier transform based method by signal mirroring. Nuclear Engineering and Design 238:10, pages 2668-2677.
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Andrej Prošek, Boris Kvizda, Borut Mavko & Tomáš Kliment. (2004) Quantitative assessment of MCP trip transient in a VVER. Nuclear Engineering and Design 227:1, pages 85-96.
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Andrej Prošek, Francesco D'Auria & Borut Mavko. (2002) Review of quantitative accuracy assessments with fast Fourier transform based method (FFTBM). Nuclear Engineering and Design 217:1-2, pages 179-206.
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