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NUCLEAR THERMAL HYDRAULICS
FRANCESCO SAVERIO D'AURIA
Academic year2023/24
CourseNUCLEAR ENGINEERING
Code1088I
Credits12
PeriodSemester 1 & 2
LanguageEnglish

ModulesAreaTypeHoursTeacher(s)
NUCLEAR THERMAL HYDRAULICSING-IND/19LEZIONI120
FRANCESCO SAVERIO D'AURIA unimap
Obiettivi di apprendimento
Learning outcomes
Conoscenze

fondamenti di fisica tecnica

Knowledge

thermotechnics and / or fluid dynamics

Modalità di verifica delle conoscenze

esame orale: tre esercizi allo studente: dopo la soluzione degli esercizi,  domande sul programma

Assessment criteria of knowledge

by oral exam (about 1.5 hour duration) 

Capacità

progetto termoidraulico dei reattori nucleari ad acqua

Skills

nuclear thermal-hydraulics technology

Modalità di verifica delle capacità

come verifica delle conoscenze

Assessment criteria of skills

oral exam (see above)

Comportamenti

risposte alle domande

Behaviors

knowlegde of nuclear technology

Modalità di verifica dei comportamenti

come da verifica di cui sopra

Assessment criteria of behaviors

oral exam (see above)

Prerequisiti (conoscenze iniziali)

fisica tecnica principalmente e/o fluidodinamica

Prerequisites

thermotechnics and / or fuid dynamics

Indicazioni metodologiche

fisica tecnica ==> esame attuale

Teaching methods

slides following the Program

Programma (contenuti dell'insegnamento)

NUCLEAR ENGINEERING COURSE’ – YEAR 2020/2021

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 & BWR RCS thermal-hydraulic design; c) The Safety Technology of NPP: the DBC, the DEC-A and DEC-B; d) The criteria for ECCS design from 10 CFR 50.46. Meaning and content of ‘Nuclear Thermal-hydraulics (NTH)’ according to recent review of NTH books (6th recommended Journal Special Issue, below).  

 

2) DESIGN OF NUCLEAR 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) pressure drops, c) balance equations, d) multi-dimensional surface for HTC (the condensation, the CHF and the reflood), e) structure of a system thermal-hydraulic code for design & transient analysis of NPP performance, f) constitutive/closure equations, g) (verification) and validation (V & V) for SYS TH codes, h) scaling and uncertainty issues, i) the BEPU approach.

 

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. The containment pressurization following LOCA

 

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 & Oskarshamn (BWR, 1988 & 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
  • Elsevier Journal ‘Nuclear Engineering and Design’ (J NED), Special Issue n. 354 (December, Ed. F. D’Auria, available from web) – 2019
  • OECD/NEA/CSNI, A state of the art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (Ed. F. D’Auria available from web) – 2017     
Syllabus

NUCLEAR ENGINEERING COURSE’ – YEAR 2020/2021

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 & BWR RCS thermal-hydraulic design; c) The Safety Technology of NPP: the DBC, the DEC-A and DEC-B; d) The criteria for ECCS design from 10 CFR 50.46. Meaning and content of ‘Nuclear Thermal-hydraulics (NTH)’ according to recent review of NTH books (6th recommended Journal Special Issue, below).  

 

2) DESIGN OF NUCLEAR 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) pressure drops, c) balance equations, d) multi-dimensional surface for HTC (the condensation, the CHF and the reflood), e) structure of a system thermal-hydraulic code for design & transient analysis of NPP performance, f) constitutive/closure equations, g) (verification) and validation (V & V) for SYS TH codes, h) scaling and uncertainty issues, i) the BEPU approach.

 

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. The containment pressurization following LOCA

 

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 & Oskarshamn (BWR, 1988 & 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
  • Elsevier Journal ‘Nuclear Engineering and Design’ (J NED), Special Issue n. 354 (December, Ed. F. D’Auria, available from web) – 2019
  • OECD/NEA/CSNI, A state of the art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (Ed. F. D’Auria available from web) – 2017     
Bibliografia e materiale didattico

vdi casella sopra

Bibliography

see above

Indicazioni per non frequentanti

è suggerto frequentare - i  on frequentati dovrebbero interloquire cn il docente

Non-attending students info

students are suggested to attend and to follow web-given lectures

Modalità d'esame

indicata sopra

Assessment methods

oral exams see above

Altri riferimenti web

vedais programma del corso

Additional web pages

see the bottom of the syllabus

Note

è suggerito frequentare le lezioni del docente

Notes

no special note

Updated: 19/07/2023 16:11