Master Degree in Nuclear Engineering: Academic year 2007-2008



Similar documents
Nuclear Design Practices and the Case of Loviisa 3

RC-17. Alejandro V. Nader National Regulatory Authority Montevideo - Uruguay

Government Degree on the Safety of Nuclear Power Plants 717/2013

Structure and Properties of Atoms

MCQ - ENERGY and CLIMATE

10 Nuclear Power Reactors Figure 10.1

ASTM C26 LONG RANGE PLAN Committee on the Nuclear Fuel Cycle

Cyber Security Design Methodology for Nuclear Power Control & Protection Systems. By Majed Al Breiki Senior Instrumentation & Control Manager (ENEC)

Loviisa 3 unique possibility for large scale CHP generation and CO 2 reductions. Nici Bergroth, Fortum Oyj FORS-seminar

Fukushima Fukushima Daiichi accident. Nuclear fission. Distribution of energy. Fission product distribution. Nuclear fuel

Nuclear Waste Management in Finland

FIRE RISK ASSESSMENT IN GERMANY - PROCEDURE, DATA, RESULTS -

Improving reactor safety systems using component redundancy allocation technique

The Fuel Cycle R&D Program. Systems Analysis

Objectives 404 CHAPTER 9 RADIATION

Safety Analysis Probabilistic Safety Assessment (PSA) for Nuclear Power Plants REGDOC-2.4.2


STATE UNIVERSITY OF NEW YORK COLLEGE OF TECHNOLOGY CANTON, NEW YORK COURSE OUTLINE CHEM COLLEGE CHEMISTRY I

Basics of Nuclear Physics and Fission

Basic principles of radioactive waste management

NUCLEAR ENGINEERING EDUCATION: A COMPETENCE-BASED APPROACH IN CURRICULA DEVELOPMENT

Nuclear Energy: Nuclear Energy

HOW DOES A NUCLEAR POWER PLANT WORK?

A Combined Nuclear Technology and Nuclear Chemistry Master A Unique Initiative at Chalmers University of Technology, Sweden

ANTEP 2015 Needs from China (NNSA)

Decommissioning situation of Nuclear Power Plant in Japan

Technical Meeting on the Implications of the Fukushima Daiichi Accident on the Safety of Fuel Cycle Facilities. IAEA Headquarters Vienna, Austria

Forensic Science Standards and Benchmarks

The Closure of the Asse Research Mine

Waste Volume Reduction by Studsvik Nuclear AB. Anders Stenmark and Bo Wirendal September 16th, 2010

Nuclear Physics. Nuclear Physics comprises the study of:

Security and Safeguards Considerations in Radioactive Waste Management. Canadian Nuclear Safety Commission

GENERAL REGULATIONS ON ENSURING SAFETY OF NUCLEAR POWER PLANTS OPB-88/97, NP (PNAE G ) Cover page. Contents

TVO and Nuclear Waste Management at Olkiluoto. Corporate Adviser

Indiana's Academic Standards 2010 ICP Indiana's Academic Standards 2016 ICP. map) that describe the relationship acceleration, velocity and distance.

9 th Grade Physical Science Springfield Local Schools Common Course Syllabi. Course Description

Nuclear Waste A Guide to Understanding Where We've Been and Where We're Going

INSPIRE GK12 Lesson Plan. The Chemistry of Climate Change Length of Lesson

Developing a Safety Case for Ontario Power Generation s L&ILW Deep Geologic Repository

Plutonium vs. Uranium: The Road Less Traveled. In a world where nuclear proliferation may no longer be held back by the guise of antiproliferation

Fission fragments or daughters that have a substantial neutron absorption cross section and are not fissionable are called...

Hazard Classification of the Remote Handled Low Level Waste Disposal Facility

RADIOACTIVE WASTE MANAGEMENT PROGRAMMES IN OECD/NEA MEMBER COUNTRIES MEXICO [2005] NATIONAL NUCLEAR ENERGY CONTEXT

ELECTRICAL ENGINEERING DEGREE. List of subjects available for 2014/2015 SCHOOL OF ENGINEERING / ESCUELA DE INGENIERÍA INDUSTRIAL UNIVERSITY OF VIGO

Safety Analysis for Nuclear Power Plants

Generating Current Electricity: Complete the following summary table for each way that electrical energy is generated. Pros:

DEMONSTRATION ACCELERATOR DRIVEN COMPLEX FOR EFFECTIVE INCINERATION OF 99 Tc AND 129 I

Office for Nuclear Regulation

IBC Nuclear Energy Liability Exclusion. Explained

Antoine Henri Becquerel was born in Paris on December 15, 1852

Nuclear Energy of Ukraine - History


Study Plan. MASTER IN (Energy Management) (Thesis Track)

IMPLEMENTATION OF A MANAGEMENT SYSTEM FOR OPERATING ORGANIZATIONS OF RESEARCH REACTORS

Checking of quality on production

INTRODUCTION. Three Mile Island Unit 2

Report WENRA Safety Reference Levels for Existing Reactors - UPDATE IN RELATION TO LESSONS LEARNED FROM TEPCO FUKUSHIMA DAI-ICHI ACCIDENT

Part 8.1. NPS Description

Chemical Decontamination and Fluid Handling Services

Categorisation of Active Material from PPCS Model Power Plants

Renewable vs. non-renewable energy sources, forms and technologies prepared by. A.Gritsevskyi, IAEA

Environmental Radiation Monitoring in Taiwan

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

How To Become A Nuclear Engineer

The International Monitoring System noble gas network Matthias Auer, CTBTO, Vienna

Ch6&7 Test. Multiple Choice Identify the choice that best completes the statement or answers the question.

Closing the CANDU Fuel Cycle

Spent Fuel Project Office Interim Staff Guidance - 17 Interim Storage of Greater Than Class C Waste

Tritium Gas Processing for Magnetic Fusion

AZ State Standards. Concept 3: Conservation of Energy and Increase in Disorder Understand ways that energy is conserved, stored, and transferred.

One Stop Shop For Teachers

Science Standard 3 Energy and Its Effects Grade Level Expectations

8 Emergency Operating Procedures (EOPs) and Severe Accident Management Guidelines (SAMGs) - Issue 06

Japan s current Nuclear Energy Policy

Trip Parameter Acceptance Criteria for the Safety Analysis of CANDU Nuclear Power Plants

ENVIRONMENTAL IMPACT ASSESSMENT REPORT

Types of Engineering Jobs

Introductions: Dr. Stephen P. Schultz

Radioactive Waste Management at Paks NPP

Lecture 14. Introduction to the Sun

Web pages and present studies related to the information on nuclear wastes management

UNESCO - EOLSS SAMPLE CHAPTER

ADVANCED NUCLEAR ENERGY SYSTEM FOR THE TWENTY-FIRST CENTURY

Economics of Thorium and Uranium Reactors

Activities of Nuclear Damage Compensation & Decommissioning Facilitation Corporation (NDF) Yasuharu Igarashi

L.S. de Carvalho, J. M de Oliveira Neto 1. INTRODUCTION IAEA-CN-164-5P01

Present status of the Swedish nuclear waste management programme. Kastriot Spahiu, SKB

Azeri, Chirag & Gunashli Full Field Development Phase 3 Environmental & Socio-economic Impact Assessment. A10.1 Introduction...

Selected aspects of the Danish repository program

SECTION TWO PACKAGING, TRANSPORTATION AND STORAGE OF RADIOACTIVE MATERIALS

Radiological mapping and characterization at the Barsebäck nuclear power plant

Estimation of Nuclear Fuel Cycle Cost and Accident Risk Cost (Statement)

Introduction to Nuclear Fuel Cycle and Advanced Nuclear Fuels

Generation IV Fast Reactors. Dr Richard Stainsby AMEC

Solar Energy Production

Transcription:

Master Degree in Nuclear Engineering: Academic year 2007-2008 Number of students 2007-2008: University Politehnica Bucharest Total: 17 Language: Romanian For further information: www.cne.pub.ro Dates Title Topics Duration ECTS Course Fall Nuclear Installations Fall Nuclear Processes From informative point is follow up the presentation of the actual and future nuclear systems specific problems, especially for the CANDU. Conception, systems, subsystems and equipment compositions are gradually presented, starting with theoretical problems and follow up with functioning, operating, safety and risk aspects and ending with economical and environment aspects. The course is based on the accumulated knowledge at the speciality courses, without superposing with these. For courses - Acknowledgement of the main types of fundamental proprieties of stable nucleuses. Atomic Nucleus (kernel); - Acknowledgement of the basic Nuclear Reactions. Classification of nuclear reactions. Reaction dynamics, conservation laws for nuclear reactions. Nuclear forces. 14 h Prof.Dr. Ilie Prisecaru 21 h Prof.Dr.phys.Gheorghe Sindilaru 1

Reaction mechanisms composed nucleus mechanism; - Acknowledgement of the Structure nuclear models. Models for the fission process. Classification of models; drop model and layer model. Fission mechanism. Occurrence conditions. Hybrid model of Sutinski; - Acknowledgement of the basic nuclear data for nuclear reactors. - Acknowledgement of the Nuclear fusion. Examples of thermonuclear fusion reactions. Plasma proprieties. Controlled thermonuclear reactions. Magnetic and inertial confining of burning plasma. For laboratory Acquiring basic knowledge specific for the activity area: o Determination of radionuclides decay time; o Example for total absorption efficiency, total interaction efficient section in Pb (determination of attenuation coefficient); o Activation analysis using * spectrometry. Example for Co-0; o Relation between energy and efficiency. o Gamma spectroscopy Acquiring of engineering special knowledge by the elaboration of a designing calculation o Acknowledgment of the basic 2

Course Fall Nuclear materials Fall Nuclear Thermal- Hydraullics/ Modelling and Simulation of NPP installations elements of the section data; o Development of the engineering calculation capacity for the calculation of gamma spectroscopy; o Capacity of using the bibliography documents in order to determine the different parameters that characterise the nuclear reaction (diagram use, selection of an analytical relation, etc.); o Development of the results interpretation and optimal version nuclear data section. Acknowledgement of the main nuclear materials; Nuclear fuel: uranium preparation, conversion and enrichment. Moderator materials Absorbers Structural materials Materials for radiological protection For Courses 1 Nuclear power primary loop design basis 2 Heat generation in nuclear reactors 3 Thermal analysis of fuel element 4 Fuel channel analysis: single phase flow case 5 Fundamentals of two phase flow Fuel channel analysis: two phase flow case 7 CHF, Critical Channel Power 8 Heat Transfer correlations applied to nuclear reactors 9 Steam Generator 14 h Prof.Dr. Petre Ghitescu 70 h Prof.Dr. Daniel Dupleac 8 3

10 Pressurizer 11 CANDU Heat Transport System 12 Transient regimes in CANDU Heat Transport System Research activity Course Fall Dissertation thesis stage Nuclear Safety Principles/ Human Risk For applications 1 CANDU Heat Transport System Design 2 : simulation of transient in CANDU Heat Transport System 3 Thermal analysis of fuel element 4 Two phase flow pressure losses calculation 5 Calculation of CCP and the post- CHF heat transfer Acknowledgement of main problems regarding radioactivity risk and of main radioactivity source in a CANDU-00 nuclear unit; Acknowledgement of the basic information regarding international and roumanian agencies/commissions for coordinate and/or requirements in nuclear area. Acknowledgement of the base elements related to the main laws and requirements (in Romania) for nuclear safety and quality management. Acknowledgement of the base elements related to the nuclear safety and nuclear reactor safety operation. Safety problems in Nuclear Power Plant Operation. 30 h Conf.dr.eng. Petre Stefanescu 4 4

Case studies. Impact of ionizing radiation on the environment Protection against ionizing radiation For courses - Acknowledgement of the main types of fundamental proprieties of stable nucleuses. Atomic Nucleus (kernel); - Acknowledgement of the basic Nuclear Reactions. Classification of nuclear reactions. Reaction dynamics, conservation laws for nuclear reactions. Nuclear forces. Reaction mechanisms composed nucleus mechanism; - Acknowledgement of the Structure nuclear models. Models for the fission process. Classification of models; drop model and layer model. Fission mechanism. Occurrence conditions. Hybrid model of Sutinski; - Acknowledgement of the basic nuclear data for nuclear reactors. - Acknowledgement of the Nuclear fusion. Examples of thermonuclear fusion reactions. Plasma proprieties. Controlled thermonuclear reactions. Magnetic and inertial confining of burning plasma. 42 h 5 Conf.dr.phys. Gheorghe Sindilaru Prof.Dr. Gheorghe Sindilaru For laboratory Acquiring basic knowledge specific 5

PSA of Nuclear Installations for the activity area: o Determination of radionuclides decay time; o Example for total absorption efficiency, total interaction efficient section in Pb (determination of attenuation coefficient); o Activation analysis using * spectrometry. Example for Co-0; o Relation between energy and efficiency. o Gamma spectroscopy Acquiring of engineering special knowledge by the elaboration of a designing calculation o Acknowledgment of the basic elements of the section data; o Development of the engineering calculation capacity for the calculation of gamma spectroscopy; o Capacity of using the bibliography documents in order to determine the different parameters that characterise the nuclear reaction (diagram use, selection of an analytical relation, etc.); o Development of the results interpretation and optimal version nuclear data section. 1. Introduction: Historical review, Safety goals, Regulation of nuclear power plant 2. Review of mathematics for PSA 3. Quantitative methods of accident analyses: Fault Tree Analyses, Event 42 Prof.Dr. Daniel Dupleac

Research activity Course Fall Trees, Alternatives to Fault Tree Analyses 4. Indentification of event initiation, plant operation state and source term 5. Nuclear Power Plant PSA: Overview of the probabilistic safety process using event trees; data base preparation, Internal and external events, PSA preparation. PSA level 1: goals and methodologies 7. PSA level 2: goals and methodologies 8. Application of PSA : PWR and CANDU case Dissertation thesis stage Radioactive waste management 1 Classification of RW. 2 The principles of RWM. 3 Generating, treatment and disposal of LLW and ILW. 4 General context and objectives of Deep Geological Disposal Concepts 5 Deep Geological Disposal Technology and key issues: Engineered Barrier Buffer Construction Technologies 7 Equipment and process for waste package emplacement in disposal cells/drifts 8 Pushing robots 9 Air / Water Cushion Technology 10 Disposal Cell/Drift Construction Concepts and Materials 8 Prof.Dr.. Petre Ghitescu 10 7

Research activity 11 Cement / bentonite interaction. Effects of alkaline fluids on host rock 12 Sources of LLW and ILW from Cernavoda NPP. Its treatment. 13 Cernavoda NPP management strategies. 14 Spent fuel from Cernavoda NPP. Storage methods. Intermediary storage of spent fuel ( DICA). 15 Romanian radioactive waste strategies. Fall Dissertation thesis stage 20 Dissertation defense 8