Nuclear Engineering Department

Science and Research Branch, Islamic Azad University

MS Reactor Physics II

Lecturer Professor Ali Pazirandeh, PhD

September 2014

3h/Week for 14 Lectures/Semester:

Nuclear fission, fission products distribution, Nuclear binding energy (MeV/nucleon), prompt neutron

energy distribution, delayed neutron distribution, number of fission neutrons vs incident neutron energy,(

5 problems.)

1. Fission, capture and scattering cross sections vs neutron energy of main reactor materials.

Resonance cross section, Breit-Wigner Formula, Temperature dependent Resonance cross

section, (5 problems). 1-2nd week

2. Six factor (SIXFAC-T) formula: To find effect of lattice-pitch on six factor plus kinf and ke). 3rd

week

3. Neutron-nucleus elastic scattering in CM and Lab system, slowing down power of different

materials in reactor core,(5 problems).4th

week

4. Neutron transport theory, neutron flux dependant 4 variables: (r, Ω, E, t), derivation of transport

equation (NTE), simplification of transport equation leading to diffusion equation, numerical

solution of diffusion equation (1-2 problems).5-6 th

week

5. Solution of diffusion equation by analytical method for homogeneous media. Solution of

modified (1⅟2 group) diffusion equation, (a multi-group diffusion equation program for a simple

medium). 2-3 problems.7th

week

6. Neutron Energy Distribution: Analytical solution in an infinite medium, slowing down energy

range, slowing down density, Fermi Age theory, neutron energy distribution in thermal range,

Maxwellian flux, neutron temperature, Multi-group neutron energy equations, mathematical

solution, 8-9th

Week

7. Resonance Absorption, resonance cross section, Doppler Broadening, practical width,

problems.10 th

week

8. Fuel Burn-up (short view) 11th

Week

9.1 Changes in Fuel Composition; Fuel Transmutation-Decay Chains; Fuel Depletion-

Transmutation-Decay Equations; Fission Products; Measure of Fuel Burn-up; Fuel Composition

Changes with Burn-up; Reactivity Effects of Fuel-Composition Changes; Compensating for

Fuel-Depletion Reactivity Effects; Reactivity Penalty; Effects of Fuel Depletion on the Power

Distribution. 12 th

Week

9.2 In-Core Fuel Management; Sm149 & Xe135 Poisoning ;Peak Xe135; Effect of Power-Level

Changes

9.3 Fertile-to-Fissile Conversion and Breeding; Conversion and Breeding Ratios; Simple Model

of

Fuel Depletion; Fuel; Physics Differences of MOX Core Surplus Weapons-Grade Uranium and

Plutonium; Composition of Weapons-Grade Uranium & Pu239 13 th

Week

9.4 Physics Differences Between Weapons- and Reactor-Grade Plutonium-Fueled Reactors;

Total Energy 14 th

Week

10 Extraction; Transmutation of Spent Nuclear Fuel; General Considerations; Conceptual Design

studies. 15 th

Week

Reference:

1. Lecture notes.

2. Hamiltom Duderstadt, Nuclear Reactor Analysis.

3. J.R.Lamarsh, Nuclear Reactor Theory.

Week

Science and Research Branch, Islamic Azad University

Faculty………………….Department…NuclEngng……Field…Nucl Reactor.

Course: ReactorPhysics II..No. of Units.3.Theory Precede Course…RPhys-I

Lecturer: Prof A.Pazirandeh…Full time……X……..Rm No 202……

1st Wk Fission, capture and scattering cross sections vs neutron energy of main reactor materials.

Resonance cross sections.

2nd Breit-Wigner Formula, Temperature dependent Resonance cross section, (5 problems).

3rd Six factor (SIXFAC-T) formula: To find effect of lattice-pitch on six factor plus kinf and

ke)

4th Neutron-nucleus elastic scattering in CM and Lab system, slowing down power of

different materials in reactor core,(5 problems).

5th Neutron transport theory, neutron flux dependent 4 variables: (r, Ω, E, t), derivation of

transport equation (NTE), 6th Simplification of transport equation leading to diffusion equation, numerical solution of

diffusion equation (1-2 problems)

7th Solution of diffusion equation by analytical method for homogeneous media.

8th Solution of modified (1⅟2 group) diffusion equation, (a multi-group diffusion equation

program for a simple medium). 2-3 problems.

9th Neutron Energy Distribution: Analytical solution in an infinite medium, slowing down

energy range, slowing down density

10th Fermi Age theory, neutron energy distribution in thermal range, Maxwellian flux, neutron

temperature, Multi-group neutron energy equations, mathematical solution

11th Resonance Absorption, resonance cross section, Doppler Broadening, practical width,

problems.

12th Fuel Burn-up (short view): Changes in Fuel Composition; Fuel Transmutation-Decay

Chains;

13th Fuel Depletion-Transmutation-Decay Equations; Fission Products; Measure of Fuel

Burn-up

14th Fuel Composition Changes with Burn-up; Reactivity Effects of Fuel-Composition

Changes;

15th Compensating for Fuel-Depletion Reactivity Effects; Reactivity Penalty; Effects of Fuel

Depletion on the Power Distribution. 12 th

Week

16th Final Examination

Reference:

4. Lecture notes.

5. Hamiltom Duderstadt, Nuclear Reactor Analysis.

6. J.R.Lamarsh, Nuclear Reactor Theory.