bases on NPP technology

thermodynamics and heat transfer

NPP technology - design and licensing

face-to-face lectures and proposing relevant documents

‘NUCLEAR ENGINEERING COURSE’ – YEAR 2017/2018

Title: ‘Thermal-hydraulics in Nuclear Technology’

Professor: F. D’Auria

The program includes six key topics as listed below. Integration lectures and Seminars will be held in the areas of ‘Core Engineering’, ‘CFD (Computational Fluid Dynamics)’, ‘Nuclear Fuel’, ‘Exploitation of Thorium’ 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 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 (BWR, 1988), 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     

• 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     

no possible or ineffective (available to discuss this topic)

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)

no

www.unipi.it

all lectures available in electronic format