Last active
October 8, 2020 14:52
-
-
Save katyhuff/c92a17ae43eb7d23f54c91d4d289f92c to your computer and use it in GitHub Desktop.
This file contains bidirectional Unicode text that may be interpreted or compiled differently than what appears below. To review, open the file in an editor that reveals hidden Unicode characters.
Learn more about bidirectional Unicode characters
% use the answers clause to get answers to print; otherwise leave it out. | |
\documentclass[11pt,answers,addpoints]{exam} | |
%\documentclass[11pt]{exam} | |
\RequirePackage{amssymb, amsfonts, amsmath, latexsym, verbatim, xspace, setspace, mathrsfs} | |
\usepackage{graphicx} | |
% By default LaTeX uses large margins. This doesn't work well on exams; problems | |
% end up in the "middle" of the page, reducing the amount of space for students | |
% to work on them. | |
\usepackage[margin=1in]{geometry} | |
\usepackage{enumerate} | |
\usepackage[hidelinks]{hyperref} | |
% Here's where you edit the Class, Exam, Date, etc. | |
\newcommand{\class}{NPRE 247} | |
\newcommand{\term}{Fall 2018} | |
\newcommand{\assignment}{HW 8} | |
\newcommand{\duedate}{2018.10.19} | |
%\newcommand{\timelimit}{50 Minutes} | |
\newcommand{\nth}{n\ensuremath{^{\text{th}}} } | |
\newcommand{\ve}[1]{\ensuremath{\mathbf{#1}}} | |
\newcommand{\Macro}{\ensuremath{\Sigma}} | |
\newcommand{\vOmega}{\ensuremath{\hat{\Omega}}} | |
% For an exam, single spacing is most appropriate | |
\singlespacing | |
% \onehalfspacing | |
% \doublespacing | |
% For an exam, we generally want to turn off paragraph indentation | |
\parindent 0ex | |
%\unframedsolutions | |
\begin{document} | |
% These commands set up the running header on the top of the exam pages | |
\pagestyle{head} | |
\firstpageheader{}{}{\makebox[0.5\textwidth]{Name: \enspace\hrulefill}} | |
\runningheader{\class}{\assignment\ - Page \thepage\ of \numpages}{Due \duedate} | |
\runningheadrule | |
\class \hfill \term \\ | |
\assignment \hfill Due \duedate\\ | |
\rule[1ex]{\textwidth}{.1pt} | |
%\hrulefill | |
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% | |
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% | |
\begin{itemize} | |
\item Show your work. | |
\item This work must be submitted online as a \textbf{single} | |
\texttt{.pdf} file through Compass2g. | |
\item Work completed with LaTeX or Jupyter earns 1 extra point. Submit | |
source file (e.g. \texttt{.tex} or \texttt{.ipynb}) along with | |
the \texttt{.pdf} file. | |
\item If this work is completed with the aid of a numerical program | |
(such as Python, Wolfram Alpha, or MATLAB) all scripts and data | |
must be submitted in addition to the \texttt{.pdf}. | |
\item If you work with anyone else, document what you worked on together. | |
\end{itemize} | |
\rule[1ex]{\textwidth}{.1pt} | |
% --------------------------------------------- | |
\begin{questions} | |
% --------------------------------------------- | |
\question (Shultis \& Faw 6.17) In a particular neutron-induced fission | |
of $^{235}U$, 4 prompt neutrons are produced and one fission fragment | |
is $^{121}Ag$. | |
\begin{parts} | |
\part[5] What is the other fission fragment? | |
\begin{solution} | |
\end{solution} | |
\part[5] How much energy is liberated promptly (i.e., before the fission fragments begin to decay)? | |
\begin{solution} | |
\end{solution} | |
\part[5] If the total initial kinetic energy of the fission fragments is 150 MeV, what is the initial kinetic energy of each? | |
\begin{solution} | |
\end{solution} | |
\part[5] What is the total kinetic energy shared by the four prompt neutrons. | |
\begin{solution} | |
\end{solution} | |
\end{parts} | |
% --------------------------------------------- | |
\question (Shultis \& Faw 6.18) Consider the following fission reaction where $^{90}Kr$ and | |
$^{142}Ba$ are the initial fission fragments. | |
\begin{align} | |
^1_0n + ^{235}U \longrightarrow ^{90}Kr + ^{142}Ba + 4 ( ^1_0n ) + 6 \gamma\\ | |
\end{align} | |
\begin{parts} | |
\part[5] What is the fission product chain created by each of these fission fragments? | |
\begin{solution} | |
\end{solution} | |
\part[5] What is the equivalent fission reaction taken to the stable end fission products? | |
\begin{solution} | |
\end{solution} | |
\part[5] How much energy is liberated promptly? | |
\begin{solution} | |
\end{solution} | |
\part[5] What is the total energy eventually emitted? | |
\begin{solution} | |
\end{solution} | |
\end{parts} | |
% --------------------------------------------- | |
\question (Shultis \& Faw 6.21) An accident in a fuel reprocessing plant, caused by improper | |
mixing of $^{235}U$, produced a burst of fission energy liberating | |
energy equivalent to the detonation of 7 kg of TNT (4.2 GJ/ton = 4.6 | |
kJ/g). About 80\% of the fission products were retained in the | |
building. | |
\begin{parts} | |
\part[5] How many fissions occurred? | |
\begin{solution} | |
\end{solution} | |
\part[5] Three months after the accident, what is the rate (W) at which energy is released by all the fission products left in the building? | |
\begin{solution} | |
\end{solution} | |
\end{parts} | |
% --------------------------------------------- | |
\question (Shultis \& Faw 7.1) A broad beam of neutrons is | |
normally incident on a homogeneous slab 6-cm thick. The intensity of | |
neutrons transmitted through the slab without inter- actions is found | |
to be 40\% of the incident intensity. | |
\begin{parts} | |
\part[5] What is the total interaction coefficient $\mu t$ for the slab | |
material? | |
\begin{solution} | |
SOLUTION HERE | |
\end{solution} | |
\part[5] What is the average distance a neutron travels in | |
this material before undergoing an interaction? | |
\begin{solution} | |
SOLUTION HERE | |
\end{solution} | |
\end{parts} | |
% --------------------------------------------- | |
\question[10] Based on the interaction coefficients tabulated in | |
Appendix C, plot the tenth- thickness (in centimeters) versus photon | |
energy from 0.1 to 10 MeV for water, concrete, iron, and lead. | |
\begin{solution} | |
\end{solution} | |
% --------------------------------------------- | |
\question Consider two adjacent infinite homogeneous slabs numbered, | |
from left to right, 1 and 2. The slab thickness and total interaction | |
coefficients are $t_i$ and $\mu_i$ (i = 1, 2). Normally incident on the | |
left slab is a beam of gamma rays. | |
\begin{parts} | |
\part[5] What is the probability a gamma rays has its first interaction slab 1? | |
\begin{solution} | |
\end{solution} | |
\part[5] What is the probability a gamma ray has its first interaction in slab 2? | |
\begin{solution} | |
\end{solution} | |
\part[5] What is the probability a gamma ray penetrates both slabs without interacting? | |
\begin{solution} | |
\end{solution} | |
\end{parts} | |
\end{questions} | |
%\bibliographystyle{plain} | |
%\bibliography{hw01} | |
\end{document} |
Sign up for free
to join this conversation on GitHub.
Already have an account?
Sign in to comment