Proposal for establishing Nuclear Reactor Safety Laboratory in Universities / Institutes

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Proposal for establishing Nuclear Reactor Safety
Laboratory in Universities / Institutes

• Dr. Ashutosh Tiwari
• Nuclear Safety Analyst, LYESPL, INDIA
• In Co-ordination with
• Dr. Chris Allison
• General Manager, ISS, US

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Table of Contents

• Generation of Nuclear Power
• Requirement of Nuclear Reactor Safety
• Path to Achieve Goal
• Introduction to Relap5
• What is Relap5
• Component Used
• Applications
• Efforts related to RELAP Code Development
• SDTP
• SDTP Members
• Benefits to SDTP Members
• Technical Support
• Training

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Path to Achieve the Goal

• Establishing Nuclear Safety Laboratories in
  Universities / Institutes.
• These laboratories will not use any Nuclear Fuel.
• No issues are related to the Safety of the
  Laboratory or its employees.
• We will train students with the help of Nuclear
  Reactor Simulator known as RELAP5.

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Introduction to RELAP5

• RELAP Reactor Excursion Leak Analysis
  Program,
• Developed at the Idaho National Engineering
  Laboratory (INEL) for the U.S. Nuclear Regulatory
  Commission (NRC),
• Basis for a nuclear plant analyzer,
• Calculates the behavior of a reactor coolant
  system during a transient,
• Used for simulation of a wide variety of
  hydraulic and thermal transients.

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Introduction to RELAP5

• Both nuclear and non-nuclear systems involving
  mixtures of steam, water, non-condensable, and
  solute can be simulated.

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Introduction to RELAP5

• RELAP5 code is based on a nonhomogeneous and
  nonequilibrium model for the two phase system.
• This system is solved by a fast, partially
  implicit numerical scheme.
• RELAP5 MOD 3.3 has been developed jointly by the
  NRC and a consortium consisting of several
  countries.

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Introduction to RELAP5

• Various Department of Energy sponsors, including
  the INTEL laboratory- directed discretionary
  funding program.
• The mission of the RELAP5 MOD 3.3 development
  program was to develop a code version suitable
  for the analysis of all transients and postulated
  accidents in LWR systems.
• Code includes component models from which general
  systems can be simulated.

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Introduction to RELAP5

• Special process models are included for effects
  such as
• Form Loss,
• Flow at an abrupt area change,
• Branching,
• Choked Flow,
• Boron Tracking,
• Non Condensable Gas Transport.

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Component Models

• Pumps
• Valves
• Pipes
• Heat Releasing Or Absorbing Structures
• Reactor Point Kinetics
• Electric Heaters

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Component Models

• Jet Pumps
• Turbines
• Separators
• Accumulators
• Control System Components

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Specific Applications
Simulations of Transient in LWR system

• Loss of coolant,
• Anticipated Transients Without Scram (ATWS)

Operational Transients

• Loss of Feed Water
• Loss of Offsite Power
• Station Blackout
• Turbine Trip

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Applications of code

• Rule Making
• Licensing Audit Calculations
• Evaluation Of Accident Mitigation Strategies
• Evaluation Of Operator Guidelines
• Experiment Planning Analysis

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Efforts to develop RELAP Code

• RELAP code embodies more than 30 years of thermal
  hydraulic and severe accident research by
  international community.
• Thousands of man-years are invested in the code
  to
• improve code performance,
• capabilities, and
• modeling accuracy

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SDTP

• SCDAP Development Training Program.
• SDTP is an international cooperative program.
• In 28 countries Nearly 60 organizations support
  Program activities.
• SDTP Program members are licensed software users.
• Innovative System Software (ISS) administers
  program.

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SDTP

• Regional Technical Support and Training Centers
  currently located in United States, Europe,
  China, and Latin America.
• Activities supported through in-kind
  contributions, membership fees, and software
  licensing fees.

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Canada McMaster University
Austria IAEA
Bulgaria Academy of Science
India Indian Institutes of Technology (4)
Czech Republic Nuclear Research Center, Rez
Croatia University of Zagreb Econet
Germany Framatome-ANP (AREVA) Forschungszentrum,
Karlsruhe Private Consultant Dr. Hagen
Italy University of Pisa
United Kingdom - University of Hertfordshire
USA Texas AM University of Missouri University
of Maryland University of Florida Ohio State
Switzerland - Paul Scherrer Institute
Lithuania Lithuanian Energy Institute
Mexico CNSNS University of Mexico
Turkey - Hacettepe University
Japan JAERI Tokyo Institute of Technology Computer
Software Dev Institute of Nuclear Safety
System NUPEC Osaka University
Korea KAERI
Romania - Universitatea Politehnica
China Shanghai Jiao Tong University Xian Jiao
Tong University Harbin University North China
Electric Power University Institute of Nuclear
Energy Technology -Tsinghua University China
institute of Atomic Energy
Spain - University of Catalunya
Indonesia - BATAN
Brazil Private Consultant Dr. Honaiser
South Africa - NECSA
Members contributing to Code Development
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Netherlands EPZ - Borselle NPP
Pakistan NPRA NPER Chasnupps 1
Russia NSI RRC Kurchatov Gidropress NIKIET OKB
Mechanical Engineering
Bulgaria - ENERGOPROEKT
India Nuclear Power Corporation of India Bhabha
Atomic Research Centre
Bangladesh AERE
Germany TÜV NORD
Ukraine STC-Energoatom
Slovak Republic - IVS Trnava
USA
Lithuania Lithuanian Energy Institute
Mexico National Institute for Nuclear Research
Japan Hitachi Electric Power Development
Co. ARTECH MHI (2) Nuclear Engineering,
Ltd Shikoku Electric Power Co. Nuclear Fuel
Industries
Romania Societatea Nationala Nuclearectrica
CNE-PROD
Peru - IPEN
Australia - ANSTO
Algeria Commissariat A L'Energie Atomique Centre
de Recherche Nucléaire d'Alger
Argentina Comisión Nacional de Energia
Atomica INVAP S.E.
South Africa ESKOM PBMR
Licensed Users Who provide Funding
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Benefits to Licensed Software User/SDTP Member

• CDs with RELAP/SCDAPSIM software executable
• Compile libraries and RELAP and SCDAP model
  source routines.
• Reference manuals
• Training tutorials
• Variety of sample problems

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Other RELAP5 Utilities

• RELSIM graphical user interface for
  RELAP/SCDAPSIM.
• Digitize Incorporate experimental or plant data
  into input models.
• Convert Incorporate strip results into input
  models.
• Stripdif Prepare plot run to compare strip
  files.

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Input Deck Library

• SDTP Members receive a portion or all of the
  extensive input deck library developed by ISS and
  other SDTP members.
• The plant library includes input models for
• Pressurized Water Reactors (PWRs)
• Boiling Water Reactors (BWRs)
• Russian Reactors (VVERs)
• Canadian Heavy Water Reactors (CANDUs)

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• Experimental facility input models include
• LOFT
• PBF
• Phebus
• CORA
• Quench
• NRU
• along with many experiment-specific input
  including the
• CORA-13
• Quench-06

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Technical Support

• Members receive technical support to solve any
  relevant problems/questions.
• Response is given within few working days.
• The technical support is typically used for
• The resolution of input problems,
• To optimize the performance of input models,
• To make modeling improvements.

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Training

• Members can attend
• Regularly scheduled SDTP-sponsored training
  workshops without paying the registration fees.
• Commercial members can attend up to two weeks of
  regularly scheduled training workshops or one
  week of individual training at a regional
  training center.
• Research and Regulatory members can attend one
  week of regularly scheduled training workshops at
  no cost.

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Training

• Members can attend
• University members can attend training workshops
  for reduced fees.
• Copies of training tutorials will be provided to
  members.

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Membership Options

• Members selecting the options to add SAMPSON or
  VISA licenses to their membership will receive
• Additional software on the member CDs.
• Additional versions that are released during the
  year,
• Can participate in any training sessions
  including this software,
• Receive any training materials prepared for the
  software.

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For further details please visit
www.lyespl.com
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Thanks
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