(THERMAL-HYDRAULICS AND CORE ENGINEERING)
CdSINGEGNERIA NUCLEARE
Codice424II
CFU12
PeriodoAnnuale
LinguaInglese
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Knowing nuclear thermal hydraulics as defined by the Elsevier Book (F. D'Auria Editor) THERMAL HYDRAULICS IN WATER-COOLED NUCLEAR REACTORS - ISBN 978-0-08-100662-7. Applications are distinguished from funamantals and the way from fundamentals to application is discussed (and of relevance).
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written and oral check. However checks are randomly made on the occasion of lectures:thisis possible considering the small number of students.
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accident analysis of NPP - DBA and BDBA as relevant. Thermotechnics with main reference to principles of thermodynamics must be handled. l
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written and oral checks - see also criteria related to knowledge above.
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NPP design criteria.Capabiity to work in a team. (also important will be to asses the skills of those who have prepared the current prospectus).
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written and oral check - see also criteria related to knowledge above
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bases of NPP technology, fundamental of thermodynamics.
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mathematics to solve (better to understanding) ODE and PDE.
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this is essential to understand NPP Safety and Design
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face-to-face lectures and proposing relevant documents -in addition continuous discussion with students as far as requested
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‘NUCLEAR ENGINEERING COURSE’ – YEAR 2017/2018
Title: ‘Thermal-hydraulics in Nuclear Technology’
Professor: F. D’Auria
The program includes three key topics as listed below. Integration lectures and Seminars will be held in the areas of ‘CFD (Computational Fluid Dynamics)’, ‘Nuclear Fuel’, and ‘Boron-Dilution-Issue’.
1) THERMAL-HYDRAULICS AND NPP TECHNOLOGY. The following sub-topics are considered: a) NPP key components and design principles; b) PWR and BWR RCS thermal-hydraulic design; c) The Safety Technology of NPP; d) The criteria for ECCS design from 10 CFR 50.46.
2) DESIGN OF NUCLER FUEL PIN. This includes the applications of the Fourier Equations and of the Fourier Law. The concepts of LHGR, MDNBR and MCHFR are introduced
3) MODELING IN NUCLEAR THERMAL-HYDRAULICS. The following sub-topics are considered: a) fundamentals including flow regimes, b) balance equations, c) multi-dimensional surface for HTC (the condensation, the CHF and the reflood), d) structure of a system thermal-hydraulic code for design & transient analysis of NPP performance, e) constitutive/closure equations, f) (verification) and validation (V & V) for SYS TH codes, g) scaling and uncertainty issues.
4) IDENTIFICATION AND CHARACTERIZATION OF THERMAL-HYDRAULIC PHENOMENA IN LWR. IT and SET phenomena are distinguished. Reference made to OECD/NEA/CSNI CCVM and to IAEA SRS 23. The boiling channel. The blow-down and the TPCF. The CCFL.
5) NATURAL CIRCULATION. NC constitutes a key IT phenomenon relevant for design and safety of NPP. Application to recent reactor technological aspects will be considered: RCS, Containment and ECCS design, SMR design. Instability in fluid-dynamics and in two-phase conditions (DWO). Reliability of NC and of passive systems.
6) THERMAL-HYDRAULIC ASPECTS OF KEY ACCIDENTS IN NPP TECHNOLOGY: Three Mile Island – 2 (PWR, 1979), Chernobyl – 4 (RBMK, 1986), La Salle and Oskarshamn (BWR, 1988 and 1999), Fukushima 1-4 (2011).
SUGGESTED BOOKS (IN ADDITION TO LECTURE MATERIAL)
- Lahey-Moody “Thermal-Hydraulics of a Boiling Water Reactor” – ANS 2nd – 1993
- Todreas-Kazimi “Nuclear Systems, I & II” – CRC (Taylor & Francis Group), 2nd – 2011
- D’Auria F. (Editor) “Thermal-hydraulics in Water Cooled Nuclear Reactors”– Elsevier – 2017
- IAEA, SRS 23 Accident Analysis (available from web) – 2002
- IAEA, SRS 52 Uncertainty Analysis (available from web) – 2008
- IAEA, SSG-2 Licensing & Thermal-hydraulics (available from web) – 2009
- OECD/NEA/CSNI, A state of the art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (available from web) – 2017
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- Lahey-Moody “Thermal-Hydraulics of a Boiling Water Reactor” – ANS 2nd – 1993
- Todreas-Kazimi “Nuclear Systems, I & II” – CRC (Taylor & Francis Group), 2nd – 2011
- D’Auria F. (Editor) “Thermal-hydraulics in Water Cooled Nuclear Reactors”– Elsevier – 2017
- IAEA, SRS 23 Accident Analysis (available from web) – 2002
- IAEA, SRS 52 Uncertainty Analysis (available from web) – 2008
- IAEA, SSG-2 Licensing & Thermal-hydraulics (available from web) – 2009
- OECD/NEA/CSNI, A state of the art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (available from web) – 2017
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no possible or ineffective (available to discuss this topic). Students must attend the Courses.
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old-style (forty years expertise of the teacher in a variety of Universities in Italy and abroad and in a variety of international T&E Courses - see the CV of the teacher).Assessment focusing on applications.
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work placement is possible at the San Piero a Grdo GRNSPG site. Work placement abroad are possible following availbaility of financing (ways to accomodate this are welcome).
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www.unipi.it, see also FONESYS and SILENCE and OECD/NEAand IAEA pages.
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all lectures available in electronic format. all lectures part of a Elsevier Book