
eBook - PDF
Reactor Physics Calculations For Applications In Nuclear Technology - Proceedings Of The Workshop
- 756 pages
- English
- PDF
- Available on iOS & Android
eBook - PDF
Reactor Physics Calculations For Applications In Nuclear Technology - Proceedings Of The Workshop
About this book
This workshop was designed to meet the needs of those currently involved in or are planning a nuclear programme involving research and/or power fission reactors. The workshop had a broad scope including not only fission reactor core calculations, but also safety, fuel management, waste disposal reactor licensing. The lectures and computer exercises covered almost all aspects of the operation of fission reactors.This workshop introduced participants to the methods currently used in fission reactor calculations and to some computer codes in which these methods are used.
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Yes, you can access Reactor Physics Calculations For Applications In Nuclear Technology - Proceedings Of The Workshop by Dermott E Cullen, R Muranaka, J J Schmidt in PDF and/or ePUB format, as well as other popular books in Biological Sciences & Science General. We have over one million books available in our catalogue for you to explore.
Information
Table of contents
- Title
- Copyright
- PREFACE
- CONTENTS
- CONTENTS OF PROCEEDINGS
- NUCLEAR DATA - THEIR IMPORTANCE AND APPLICATION IN FISSION REACTOR PHYSICS CALCULATIONS
- Activities of the NEA Reactor Physics Committee and International Benchmark Studies for Reactor Physics Codes.
- Activities of the OECD/ NEA Data Bank and its Computer Program Service
- NJOY: A Comprehensive System for the Processing of ENDF Formatted Nuclear Data
- NJOY-89 Computer Exercises
- Evaluated Nuclear Data Processing and Nuclear Reactor Calculations
- Basic Reactor Physics
- LATTICE CELL CALCULATIONS, SLOWING DOWN THEORY AND COMPUTER CODE WIMS; VVER TYPE REACTORS
- PREPARATION OF INPUT FOR THE WIMS CODE
- IN CORE FUEL MANAGEMENT: PWR Group Constants Generation Using PSU-LEOPARD Code
- IN-CORE FUEL MANAGEMENT: PWR Core Calculations Using MCRAC
- Nuclear Safety Parameters of Mixed TRIGA Cores
- Optimization of TRIGA Reactor Operation Using Reactor Calculations
- COMPUTER CODE ANISN MULTIPLYING MEDIA AND SHIELDING CALCULATION I. THEORY
- COMPUTER CODE ANISN MULTIPLYING MEDIA AND SHIELDING CALCULATION II. CODE DESCRIPTION (INPUT/OUTPUT)
- COMPUTER CODE ANISN MULTIPLYING MEDIA AND SHIELDING CALCULATION III. SAMPLE PROBLEMS
- Inverse point kinetics for the reactivity Determination - Description of the KINIK Code
- Fluid Flow and Heat transfer Model of the HEATHYD Code
- REACTOR NEUTRON DOSIMETRY Radiation Damage Estimates for Reactor Structural Materials
- REACTOR NEUTRON DOSIMETRY - CALCULATION METHODS IN NEUTRON SPECTRUM UNFOLDING
- REACTOR NEUTRON DOSIMETRY - PAST, PRESENT and FUTURE
- Advances in Personal Computers for Scientific Applications
- Review of Research Reactor Safety Documentation developed by the International Atomic Energy Agency
- FINAL LIST OF PARTICIPANTS