پایان نامه با کلید واژه های Interaction، ACT

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ABSTRACT
TO DETERMINE TWO SAFETY COEFFICIENTS OF VVER-1000 REARCTOR CORE INCLUDING HEXAGONAL ANNULAR FUEL ASSEMBLIES
BY
ALI ERFANI NIA
A proposed design for the next generation PWRs and BWRs to achieve more average power density and lower fuel maximum temperature is consideration of annular fuel in core of these types of reactors without changing dimensions of the core and fuel assemblies (FAs). There is few study has done on VVER-1000 reactors with annular fuel. Our aim herein is to study two important safety coefficients of a typical VVER-1000 reactor core including hexagonal annular fuel assemblies at the beginning of the cycle (BOC). These are 1. “ prompt reactivity coefficient ” that is an important factor in study of power excursions that is calculated -1.23×〖10〗^(-13) (1/j) and 2.“ power reactivity coefficient ” that is an important factor that gives idea of about reactivity changes during power maneuver for a power reactor that is calculated 4.98×〖10〗^(-10) (1/w). All investigation are made using MCNP-5 code.
IN THE NAME OF GOD
TO DETERMINE TWO SAFETY COEFFICIENTS OF VVER-1000 REARCTOR CORE INCLUDING HEXAGONAL ANNULAR FUEL ASSEMBLIES
BY
ALI ERFANI NIA
THHESIS
SUBMITTED TO THE SCHOOL OF GRADUATE STUDIES IN PARTIAL FULFILLMENT OF THE REQUIREMENTS FOR THE DEGREE OF MASTER OF SCIENCE (MSc.)
IN
NUCLEAR ENGINEERING
SHIRAZ UNIVERSITY
SHIRAZ
ISLAMIC REPUBLIC OF IRAN
EVALUATED AND APPROVED BY THE THESIS COMMITTEE AS : EXCELLENT
………………………… F. FAGHIHI, ASSOCIATE PROF. OF NUCLEAR
ENGINEERING, SHIRAZ UNIVERSITY.
………………………… K. HADAD, ASSOCIATE PROF. OF NUCLEAR
ENGINEERING, SHIRAZ UNIVERSITY.
…………………………..KH. JAFARPUR, ASSOCIATE PROF. OF MECHNICAL
ENGINEERING, SHIRAZ UNIVERSITY.
…………………………. R. FAGHIHI, ASSISTANT PROF. OF NUCLEAR
ENGINEERING, SHIRAZ UNIVERSITY.
JANUARY 2012
Shiraz University
Faculty of Mechanical Engineering
M.S. Thesis in
Nuclear Engineering
TO DETERMINE TWO SAFETY COEFFICIENTS OF VVER-1000 REARCTOR CORE INCLUDING HEXAGONAL ANNULAR FUEL ASSEMBLIES
By
ALI ERFANI NIA
Supervised by
Dr. F. Faghihi
Dr. K. Hadad
January 2012
1Energy Information Administration
1Pressure Tube
2Pressure Vessel
3On-line Refueling
1Presurized Water Reactor
2Fission Products Barrier
1 Fast Neutrons
1Self Regulating
1 Primary Safety Analysis Report
2Final Safety Analysis Report
3Quality Assurance Manual
1Neutron Transport Equation
1Discretization Methods
2Probabilistic
1Random Number Generator
2Central Limit Theorem
1 Vibration-Packing fuel with internal and external cooling
18Pellet-Clad Mechanical Interaction
1Minimum Departure from Nucleate Boiling Ratio
2Peak Clad Temperature
3Loss of Coolant Accident
1Minimum departure from nucleate boiling ratio
1Burnable Absorber Rod
1- Control and Protection System Absorber Rod
1Under Moderated
2Over Moderated
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