NucE 309
Homework 16 Intro to PDEs
Due 10/16/2015
Name:
Collaborators:
Problems:
1. Complete the EFTE survey on Angel. State in the homework whether you
completed it.
2. Pg. 542
3.
17.
19.
2. Later in this section we will spend several assignments using M
NucE 309
Homework 13 Gauss-Seidel
Due 10/5/2015
Computer Assignment, to be done with Matlab or Octave
Name:
Name:
Problems:
1. Pg. 863
5. Do only two iterations using Eq. (6). Ignore the instructions about 6S. Do
this problem on paper, NOT IN MATLAB.
2. G
NucE 309
Homework 20 The Finite Difference Method
Due 10/30/2015
Parts of this homework will be done on the computer. It can be completed in
matlab, octave, or C+. However, code will only be supplied in matlab (it
should work in octave, but I will not tes
NucE 309: Analytical Techniques for Nuclear Concepts
Fall 2015, MWF 1:25 2:15 p.m., 135 Reber Building
Instructor:
Dr. Michael R Tonks, 233 Reber, 863-1323, mrt5296@psu.edu
Office Hours: T 9:00-10:00 a.m., Th 9:00-10:00 a.m. or by appointment.
Teaching As
NUCLEAR REACTOR ANALYSIS
NucE 403
2015
Dr. Marek Flaska
Chapter 5
Mid-Term Course Evaluations
Your feedback is appreciated!
Up to 5 points of extra credit can be earned
2
Homework #2
It was assigned last Monday
Take a look at Angel for details
Due on next
NucE 403
ADVANCED REACTOR DESIGN
Fall 2015
Dr. Marek Flaska
Introduction
We are Nuclear Engineers!
2
Course Summary
o This course is one of the most fundamental topics of nuclear
engineering
o Prerequisites: NucE 302
o Requires fundamental knowledge and s
NUCLEAR REACTOR ANALYSIS
NucE 403
2015
Dr. Marek Flaska
Chapter 5
Mid-Term Course Evaluations
Your feedback is appreciated!
Up to 5 points of extra credit can be earned
2
Homework #2
It will be assigned this afternoon
Take a look at Angel for details
Due
NUCLEAR REACTOR ANALYSIS
NucE 403
2015
Dr. Marek Flaska
Chapter 5
Homework Format
The expected homework format was described in the course syllabus
Use the syllabus as a template
Easy way to avoid losing points
Expected sections:
Introduction - Brief
NUCLEAR REACTOR ANALYSIS
NucE 403
2015
Dr. Marek Flaska
Chapter 5
Neutron Diffusion Theory
After completing this chapter, students should have
a thorough understanding of:
One speed diffusion theory and its limitations
Initial and boundary conditions
Neut
NucE 403
ADVANCED REACTOR DESIGN
2015
Dr. Marek Flaska
Chapter 2 Review continued
1
Neutron cross section hierarchy
2
= a + s + in + n, p + n,a
T
a = c + f
3
DFFERENTIAL SCATTERING CROSS SECTIONS
o
Concept of differential scattering cross-section
o
Cosi
NUCLEAR REACTOR ANALYSIS
NucE 403
2015
Dr. Marek Flaska
Chapter 3
Decay of the 87Br delayed neutron precursor
2
3
Fission Cross-Sections
Fission cross-section for fissile nuclides
three regions of energy dependence
Three regions 1/v, resonance, and
smo
NucE 403
ADVANCED REACTOR DESIGN
2015
Dr. Marek Flaska
Chapter 2 - Review
1
Neutron Nuclear Reactions
INTRODUCTION
o
The primary function of a nuclear reactor
is the utilization of energy released by
a controlled chain reaction of nuclear fission
events m
Department Of Mechanical And Nuclear Engineering
NucE430
Chapter 2. Nuclear Reactor Power Systems
2.2 Nuclear Power Reactors
By
Seungjin Kim
Associate Professor
Mechanical and Nuclear Engineering
The Pennsylvania State U
Department Of Mechanical And Nuclear Engineering
NucE430
Chapter 2. Nuclear Power Reactor Systems
2.1 Denitions of Nuclear Engineering Terms:
Major Reactor Components
By
Seungjin Kim
Associate Professor
Mechanical and N
NUCE430 DESIGN PRINCIPLES OF REACTOR SYSTEMS
Assignment #2
Name:
Score:
of 140
Show all the steps in presenting the solutions to receive full credit.
1.
(30 pts) Refer to Tables 1.3 and 2.1 (shown in the Appendix section at the end of the problem
sheet) a
Department Of Mechanical And Nuclear Engineering
NucE430
Design Principles of Reactor System
Review of Course Syllabus
By
Seungjin Kim
Associate Professor
Mechanical and Nuclear Engineering
The Pennsylvania State University