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Scheda Riassuntiva
Anno Accademico 2018/2019
Scuola Scuola di Ingegneria Industriale e dell'Informazione
Insegnamento 091727 - SAFETY ASSESSMENT OF RADIOACTIVE WASTE REPOSITORIES
Docente Zio Enrico
Cfu 5.00 Tipo insegnamento Monodisciplinare

Corso di Studi Codice Piano di Studio preventivamente approvato Da (compreso) A (escluso) Insegnamento
Ing Ind - Inf (Mag.)(ord. 270) - BV (478) NUCLEAR ENGINEERING - INGEGNERIA NUCLEARE*AZZZZ091727 - SAFETY ASSESSMENT OF RADIOACTIVE WASTE REPOSITORIES

Obiettivi dell'insegnamento

The primary goal of this course is to provide the students with the adequate competence on methods and techniques for the assessment of the safety performance of a radioactive waste repository, which requires the systematic analysis of the performance of the engineered and natural barriers of protection against radionuclide release and dispersion.


Risultati di apprendimento attesi

ELO 1: The student learns the options and designs for radioactive waste disposal.

ELO 2: The student knows the systematic procedure for i) the identification of the potential scenarios of release of radioactive wastes from a repository (features, events and processes), ii) the estimation of the scenarios occurrence probabilities and consequences, and iii) the evaluation of the uncertainties associated to these estimates.

ELO 3: the student applies techniques for the treatment of uncertainty in the safety performance assessment of a radioactive waste repository and formulates judgements on the confidence in the results of the safety performance assessment, for robust decision-making.

ELO 4: the student learns how to communicate the results of a safety performance assessment of a radioactive waste repository.

ELO 5: the student autonomously identifies advanced methods and techniques for the safety performance assessment of radioactive waste repository in the scientific literature, and understands and applies them.


Argomenti trattati

General framework of risk analysis

 Problem setting 

  1. Course Introduction;
  2. Waste categories and sources; Regulations and IAEA standards
  3. Waste treatment and disposal options: Near surface LILW and Geologic HLW disposal (near-field, far-field environments)
  4. Features, Events and Processes involved in the safety performance assessment of a radioactive waste repository.

 Probabilistic approach to Safety Performance Assessment

 Near-field analysis

 Far-field analysis

 Consequence estimation

  1. Groundwater transport modelling by the classical Advection Dispersion Equation
  2. Parameter estimation: laboratory tests and field scale experiments
  3. Groundwater transport modelling by simulation methods

 Analytical and simulations methods for solving contaminant transport problems

 Sensitivity and uncertainty analysis

  1. General theory 
  2. Sample-based approaches and computation acceleration methods (Variance reduction approached and meta-modeling)

Prerequisiti
 

Modalità di valutazione

The evaluation consists in an oral part.

The oral exam aims at verifying i) the student knowledge on the alternatives of radioactive waste disposal (ELO 1) and his/her understanding of the systematic procedure for the identification of the potential release scenarios caused by the release of radioactive wastes from the repository, the estimation of their probabilities and consequences, and the evaluation of the uncertainties associated to these estimates (ELO 2), ii) the student ability to treat the uncertainty in the safety performance of a radioactive waste repository and to make judgments on the confidence in the results obtained, for robust decision-making (ELO 3), the communication skill on the results of a safety performance assessment (ELO 4) and the ability of autonomously identifying the proper methods and techniques for performance safety assessment. The oral part of the exam will contribute to 100% of the final grade.


Bibliografia
Risorsa bibliografica obbligatoriaEdoardo Tosoni, Ahti Salo and Enrico Zio, Scenario Analysis for the Safety Assessment of Nuclear Waste Repositories: A Critical Review, Editore: Risk Analysis, Anno edizione: 2017
Risorsa bibliografica obbligatoriaD. Savage, The scientific and regulatory basis for the geological disposal of radioactive waste, Editore: Wiley&Sons, Anno edizione: 1995
Risorsa bibliografica obbligatoriaJ. C. Helton and C. J. Sallaberry, Conceptual basis for the definition and calculation of expected dose in performance assessment for the proposed high-level radioactive waste repository at Yucca Mountain, Nevada, Editore: Reliability Engineering and System Safety, Anno edizione: 2008
Risorsa bibliografica obbligatoriaNUREG-1573, A performance assessment methodology for low-level radioactive waste disposal facility, Anno edizione: 2000
Risorsa bibliografica obbligatoriaNear surface disposal of radioactive waste, Editore: IAEA Safety Standards Series - Requirements, WS-R-1, Anno edizione: 1999
Risorsa bibliografica obbligatoriaSafety assessment of near surface disposal of radioactive waste, Editore: IAEA Safety Standards Series - Safety Guide, WS-G-1.1, Anno edizione: 1999
Risorsa bibliografica obbligatoriaClassification of Radioactive Waste, Editore: IAEA Series - A safety guide, 111-G-1.1, Anno edizione: 1994

Forme didattiche
Tipo Forma Didattica Ore di attività svolte in aula
(hh:mm)
Ore di studio autonome
(hh:mm)
Lezione
32:30
48:45
Esercitazione
17:30
26:15
Laboratorio Informatico
0:00
0:00
Laboratorio Sperimentale
0:00
0:00
Laboratorio Di Progetto
0:00
0:00
Totale 50:00 75:00

Informazioni in lingua inglese a supporto dell'internazionalizzazione
Insegnamento erogato in lingua Inglese
schedaincarico v. 1.6.1 / 1.6.1
Area Servizi ICT
02/04/2020