From 67d86b1856e1ddabf7455d07f0a2fb8b864c1e6f Mon Sep 17 00:00:00 2001 From: Jin Whan Bae Date: Wed, 6 Sep 2017 19:55:36 -0500 Subject: [PATCH] review fixes --- acros.tex | 14 ++-- appendix.tex | 67 ++++++++++++++++++ arfc-pres.tex | 21 +++--- background.tex | 60 +++++++++++----- case_specification.tex | 156 +++++++++-------------------------------- conclusion.tex | 4 +- future.tex | 8 ++- results.tex | 18 ++--- 8 files changed, 179 insertions(+), 169 deletions(-) create mode 100644 appendix.tex diff --git a/acros.tex b/acros.tex index 5b17a3d..4fc4484 100644 --- a/acros.tex +++ b/acros.tex @@ -1,12 +1,11 @@ %\newacronym{<++>}{<++>}{<++>} -\newacronym{MTHM}{MTHM}{metric ton of heavy metal} +\newacronym[longplural={metric tons of heavy metal}]{MTHM}{MTHM}{metric ton of heavy metal} \newacronym{ABM}{ABM}{agent-based modeling} \newacronym{ACDIS}{ACDIS}{Program in Arms Control \& Domestic and International Security} \newacronym{ADS}{ADS}{Accelerator-Driven Systems} \newacronym{AHTR}{AHTR}{Advanced High Temperature Reactor} \newacronym{ANDRA}{ANDRA}{Agence Nationale pour la gestion des D\'echets RAdioactifs, the French National Agency for Radioactive Waste Management} -\newacronym{ANL}{ANL}{Argonne Natio -\newacronym{MTHM}{MTHM}{metric ton of heavy metal}nal Laboratory} +\newacronym{ANL}{ANL}{Argonne National Laboratory} \newacronym{ANS}{ANS}{American Nuclear Society} \newacronym{API}{API}{application programming interface} \newacronym{ARE}{ARE}{Aircraft Reactor Experiment} @@ -39,7 +38,7 @@ \newacronym{DSNF}{DSNF}{DOE spent nuclear fuel} \newacronym{DYMOND}{DYMOND}{Dynamic Model of Nuclear Development } \newacronym{EBS}{EBS}{Engineered Barrier System} -\newacronym{EDF}{EDF}{Électricité de France} +\newacronym{EDF}{EDF}{\{E}lectricit`{e} de France}` \newacronym{EDZ}{EDZ}{Excavation Disturbed Zone} \newacronym{EIA}{EIA}{U.S. Energy Information Administration} \newacronym{EPA}{EPA}{Environmental Protection Agency} @@ -97,6 +96,7 @@ \newacronym{MSBR}{MSBR}{Molten Salt Breeder Reactor} \newacronym{MSRE}{MSRE}{Molten Salt Reactor Experiment} \newacronym{MSR}{MSR}{Molten Salt Reactor} +\newacronym{MTHM}{MTHM}{metric ton of heavy metal} \newacronym{NAGRA}{NAGRA}{National Cooperative for the Disposal of Radioactive Waste} \newacronym{NEAMS}{NEAMS}{Nuclear Engineering Advanced Modeling and Simulation} \newacronym{NEUP}{NEUP}{Nuclear Energy University Programs} @@ -123,7 +123,7 @@ \newacronym{PRIS}{PRIS}{Power Reactor Information System} \newacronym{PRKE}{PRKE}{Point Reactor Kinetics Equations} \newacronym{PSPG}{PSPG}{Pressure-Stabilizing/Petrov-Galerkin} -\newacronym{PWAR}{PWAR}{Pratt and Whitney Aircraft Reactor} +\newacronym{PWAR}{PWAR}{Pratt and Whitney Aircraft REeactor} \newacronym{PWR}{PWR}{Pressurized Water Reactor} \newacronym{PyNE}{PyNE}{Python toolkit for Nuclear Engineering} \newacronym{PyRK}{PyRK}{Python for Reactor Kinetics} @@ -142,11 +142,11 @@ \newacronym{SUPG}{SUPG}{Streamline-Upwind/Petrov-Galerkin} \newacronym{SWF}{SWF}{Separations and Waste Forms} \newacronym{SWU}{SWU}{Separative Work Unit} +\newacronym{ThOX}{ThOX}{thorium oxide} \newacronym{TRIGA}{TRIGA}{Training Research Isotope General Atomic} \newacronym{TRISO}{TRISO}{Tristructural Isotropic} \newacronym{TSM}{TSM}{Total System Model} \newacronym{TSPA}{TSPA}{Total System Performance Assessment for the Yucca Mountain License Application} -\newacronym{ThOX}{ThOX}{thorium oxide} \newacronym{UFD}{UFD}{Used Fuel Disposition} \newacronym{UML}{UML}{Unified Modeling Language} \newacronym{UNF}{UNF}{Used Nuclear Fuel} @@ -158,4 +158,4 @@ \newacronym{VVER}{VVER}{Voda-Vodyanoi Energetichesky Reaktor (Russian Pressurized Water Reactor)} \newacronym{VV}{V\&V}{verification and validation} \newacronym{WIPP}{WIPP}{Waste Isolation Pilot Plant} -\newacronym{YMR}{YMR}{Yucca Mountain Repository Site} +\newacronym{YMR}{YMR}{Yucca Mountain Repository Site} \ No newline at end of file diff --git a/appendix.tex b/appendix.tex new file mode 100644 index 0000000..488533f --- /dev/null +++ b/appendix.tex @@ -0,0 +1,67 @@ +\begin{frame} +\frametitle{Composition of fresh and spent fuel} + Reference depletion calculation from ORGIEN was used (also used in \cite{wilson_adoption_2009}). + \begin{table}[h] + \centering + \scalebox{0.26}{ + \begin{tabular}{|c|c|c|c|c|c|c|} + \hline + Isotope & Fresh UOX Fuel & Spent UOX Fuel (BU: $51\frac{GWdth}{MTHM}$) & Fresh SFR Fuel & Spent SFR Fuel \\ \hline + He4 & & 9.474E-07 & & 7.827E-06 \\ \hline + Ra226 & & 9.788E-14 & & 5.151E-14 \\ \hline + Ra228 & & 2.750E-20 & & 4.904E-21 \\ \hline + Pb206 & & 5.574E-18 & & 1.210E-18 \\ \hline + Pb207 & & 1.685E-15 & & 1.892E-16 \\ \hline + Pb208 & & 3.688E-12 & & 5.875E-11 \\ \hline + Pb210 & & 3.023E-19 & & 8.143E-18 \\ \hline + Th228 & & 8.475E-12 & & 1.004E-10 \\ \hline + Th229 & & 2.727E-12 & & 4.065E-12 \\ \hline + Th230 & & 2.625E-09 & & 2.139E-09 \\ \hline + Th232 & & 4.174E-10 & & 4.425E-11 \\ \hline + Bi209 & & 6.607E-16 & & 2.600E-14 \\ \hline + Ac227 & & 3.096E-14 & & 4.840E-15 \\ \hline + Pa231 & & 9.246E-10 & & 1.300E-10 \\ \hline + U232 & & 0.000 & & 0.000 \\ \hline + U233 & & 2.213E-09 & & 5.528E-09 \\ \hline + U234 & 0.000& 0.000 & & 0.000 \\ \hline + U235 & 0.032& 0.007 & 0.002 & 0.000 \\ \hline + U236 & & 0.005 & & 0.000 \\ \hline + U238 & 0.968& 0.920 & 0.887 & 0.808 \\ \hline + Np237 & & 0.000 & & 0.000 \\ \hline + Pu238 & & 0.000 & 0.001 & 0.001 \\ \hline + Pu239 & & 0.006 & 0.060 & 0.085 \\ \hline + Pu240 & & 0.002 & 0.027 & 0.027 \\ \hline + Pu241 & & 0.001 & 0.014 & 0.003 \\ \hline + Pu242 & & 0.000 & 0.005 & 0.001 \\ \hline + Pu244 & & 2.864E-08 & 1.508E-07 & 5.461E-09 \\ \hline + Am241 & & 6.442E-05 & & 0.001 \\ \hline + Am242m & & 8.533E-07 & & 7.961E-05 \\ \hline + Am243 & & 0.000 & & 0.000 \\ \hline + Cm242 & & 2.589E-05 & & 5.331E-05 \\ \hline + Cm243 & & 0.000 & & 3.242E-06 \\ \hline + Cm244 & & 8.561E-05 & & 0.000 \\ \hline + Cm245 & & 5.721E-06 & & 3.936E-05 \\ \hline + Cm246 & & 7.295E-07 & & 1.434E-05 \\ \hline + Cm247 & & 0.000 & & 5.317E-07 \\ \hline + Cm248 & & 7.691E-10 & & 0.000 \\ \hline + Cm250 & & 4.280E-18 & & 6.407E-15 \\ \hline + Cf249 & & 1.649E-12 & & 6.446E-10 \\ \hline + Cf250 & & 2.041E-12 & & 6.703E-11 \\ \hline + Cf251 & & 9.865E-13 & & 1.903E-12 \\ \hline + Cf 252 & & 6.579E-13 & & 4.014E-14 \\ \hline + H3 & & 8.584E-08 & & 1.747E-07 \\ \hline + C14 & & 4.057E-11 & & \\ \hline + C Other & & & & \\ \hline + Kr81 & & 4.216E-11 & & 8.038E-12 \\ \hline + Kr85 & & 3.444E-05 & & 2.950E-05 \\ \hline + Kr Other & & 0.000 & & 0.000 \\ \hline + Sr90 & & 0.001 & & 0.001 \\ \hline + Sr Other & & 0.000 & & 0.000 \\ \hline + Tc99 & & 0.000 & & 5.391E-05 \\ \hline + Tc Other & & 0.000 & & 0.002 \\ \hline + + \end{tabular}} + \caption{Fresh and Spent Fuel Compositions} + \label{tab:comp} +\end {table} +\end{frame} \ No newline at end of file diff --git a/arfc-pres.tex b/arfc-pres.tex index bba8b91..01eebcb 100644 --- a/arfc-pres.tex +++ b/arfc-pres.tex @@ -7,11 +7,11 @@ \documentclass[9pt]{beamer} \usetheme[white]{Illinois} %\title[short title]{long title} -\title[Short Title]{Synergistic Spent Nuclear Fuel Dynamics Within the European Union} +\title[Synergistic Spent Nuclear Fuel Dynamics Within the European Union]{Synergistic Spent Nuclear Fuel Dynamics Within the European Union} %\subtitle[short subtitle]{long subtitle} -\subtitle[Short SubTitle]{French Transition into SFRs} +\subtitle[French Transition into SFRs]{French Transition into SFRs} %\author[short name]{long name} -\author[Your Name]{Jin Whan Bae, Kathyrn Huff, Clifford Singer \\ Advanced Reactors and Fuel Cycles Group} +\author[Jin Whan Bae, Kathryn Huff, Clifford Singer]{Jin Whan Bae, Kathryn Huff, Clifford Singer \\ Advanced Reactors and Fuel Cycles Group} %\date[short date]{long date} \date[10.22.2017]{October 22, 2017} %\institution[short name]{long name} @@ -55,8 +55,11 @@ \usepackage{booktabs} % nice rules (thick lines) for tables \usepackage{microtype} % improves typography for PDF \usepackage{xspace} - \usepackage{tabularx} +\usepackage[affil-it]{authblk} +\usepackage{tikz} +\usepackage{cleveref} +\usepackage{datatool} \newcolumntype{b}{X} \newcolumntype{s}{>{\hsize=.5\hsize}X} \newcolumntype{m}{>{\hsize=.75\hsize}X} @@ -68,12 +71,8 @@ \newcommand{\ud}{\mathop{}\!\mathrm{d}} % upright derivative symbol \newcommand{\Cyclus}{\textsc{Cyclus}\xspace}% \graphicspath{ {images/} } -\usepackage[affil-it]{authblk} -\usepackage{tikz} \usetikzlibrary{positioning, arrows, decorations, shapes } -\usepackage{cleveref} -\usepackage{datatool} \begin{document} %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% %% From uw-beamer Here's a handy bit of code to place at @@ -111,15 +110,17 @@ \section{Background} \section{Scenario Specification} \input{case_specification} -\section{Future Predictions} +\section{Predictions} \input{future} \section{Results} \input{results} -\section{Conclusion / Discussion} +\section{Conclusion} \input{conclusion} +\section{Appendix} +\input{appendix} %%--------------------------------%% %%--------------------------------%% diff --git a/background.tex b/background.tex index 3ab140a..ebb5940 100644 --- a/background.tex +++ b/background.tex @@ -1,27 +1,28 @@ -\subsection{Background} +\subsection{Motivation} \begin{frame} \frametitle{Background} \begin{itemize} - \item France - preparation for a transition from LWRs to SFRs \cite{noauthor_cne2_nodate} - \item France - additional LWR construction to supply Plutonium for SFR transition - \item Most EU nations do not have a repository for UNF + \item France - preparation for a transition from \glspl{LWR} to \glspl{SFR} \cite{noauthor_reports_2015} + \item France - additional LWR construction to supply Plutonium for \gls{SFR} transition + \item Most EU nations do not have a repository for \gls{UNF} \end{itemize} \end{frame} \begin{frame} - \frametitle{Abstract} - By taking UNF from other EU nations, France can transition into a fully SFR fleet (66 GWe) - without additional construction of LWRs. + \frametitle{Summary} + By taking \gls{UNF} from other EU nations, France can transition into a fully \gls{SFR} fleet (66 GWe) + without additional construction of \glspl{LWR}. \begin{itemize} - \item 66 GWe -> 110 ASTRID-type SFRs - \item Collaborative approach seeks to benefit both sides + \item Transition to 110 ASTRID-type \glspl{SFR} (Capacity 66 GWe) + \item Collaborative approach benefits both sides \end{itemize} \end{frame} \begin{frame} \frametitle{Literature Review} + Past research is mostly on: \begin{itemize} - \item French transition into SFR after additional construction of EPRs + \item French transition to \glspl{SFR} after additional construction of \glspl{EPR} \cite{carre_overview_2009, martin_symbiotic_2017, freynet_multiobjective_2016} \item partitioning and transmutation in a regional (European) context \cite{fazio_study_2013} \end{itemize} @@ -29,21 +30,46 @@ \subsection{Background} \subsection{Method and Specfications} +\begin{frame} + \frametitle{Cyclus} + \Cyclus \cite{huff_fundamental_2016} is the next generation agent-based nuclear + fuel cycle simulator. + \begin{minipage}[b]{.45\linewidth} + \begin{itemize} + \item Flexibility to users and developers through a dynamic resource exchange solver + \item user-developed agent framework + \item low barrier to entry for new users and developers + \item expanding ecosystem + \end{itemize} + \end{minipage} + \hspace{.5cm} + \begin{minipage}[b]{.45\linewidth} + \begin{figure} + \begin{center} + \includegraphics[width=\textwidth]{./images/cyclus/png} + \end{center} + % does this need a caption? + \end{figure} + \end{minipage} + +\end{frame} + + \begin{frame} \frametitle{Method} - \Cyclus, the agent-based simulator \cite{huff_fundamental_2016} is used. Two simulations are run: \begin{itemize} - \item EU UNF inventory at 2050 (1970-2050) - \item French transition to SFRs (1970-2160) + \item \gls{EU} \gls{UNF} inventory at 2050 (1970-2050) + \item French transition to \glspl{SFR} (1970-2160) \end{itemize} - The UNF and tails inventory from the first simulation is used for the second simulation. + The \gls{UNF} and tails inventory from the first simulation are used for the second simulation. \end{frame} \begin{frame} \frametitle{Deployment Timeline for EU historical operation} - Historical operation and predictions are made using references such as IAEA PRIS \cite{iaea_pris_nodate}, - World Nuclear Association \cite{world_nuclear_association_nuclear_2017} and other papers + Historical operation and predictions are made using references such as \gls{IAEA} \gls{PRIS} \cite{iaea_pris_2017}, + World Nuclear Association \cite{world_nuclear_association_nuclear_2017} and papers on the + future of nuclear power \cite{joskow_future_2012, hatch_politics_2015}. \begin{figure}[htbp!] \begin{center} @@ -57,7 +83,7 @@ \subsection{Method and Specfications} \begin{frame} \frametitle{Deployment Timeline for French Transition} - 600 MWe SFRS are deployed to a capacity of 66,000 MWe by 2076. + 110 \glspl{SFR} (66 GWe) are deployed by 2076. \begin{figure}[htbp!] \begin{minipage}[b]{.45\linewidth} \begin{center} diff --git a/case_specification.tex b/case_specification.tex index 1e9f5d1..b50c812 100644 --- a/case_specification.tex +++ b/case_specification.tex @@ -13,9 +13,10 @@ \subsection{Assumptions} \frametitle{Assumptions} \begin{itemize} \item SFR technology available for deployment in 2040. + \item French nuclear electricity demand remains static at 66 GWe. \item Decay is not taken into account. \item Reactor construction is always completed on time. - \item Separated Uranium is unused and stockpiled. + \item Separated uranium is unused and stockpiled. \item LWRs have a lifetime of 60 years, unless shut down prematurely. \item SFRs have a lifetime of 80 years. \end{itemize} @@ -27,74 +28,6 @@ \subsection{Assumptions} \end{itemize} \end{frame} -\begin{frame} - \frametitle{Composition of fresh and spent fuel} - Reference depletion calculation from ORGIEN was used (also used in \cite{wilson_adoption_2009}). - \begin{table}[h] - \centering - \scalebox{0.26}{ - \begin{tabular}{|c|c|c|c|c|c|c|} - \hline - Isotope & Fresh UOX Fuel & Spent UOX Fuel (BU: $51\frac{GWdth}{MTHM}$) & Fresh SFR Fuel & Spent SFR Fuel \\ \hline - He4 & & 9.474E-07 & & 7.827E-06 \\ \hline - Ra226 & & 9.788E-14 & & 5.151E-14 \\ \hline - Ra228 & & 2.750E-20 & & 4.904E-21 \\ \hline - Pb206 & & 5.574E-18 & & 1.210E-18 \\ \hline - Pb207 & & 1.685E-15 & & 1.892E-16 \\ \hline - Pb208 & & 3.688E-12 & & 5.875E-11 \\ \hline - Pb210 & & 3.023E-19 & & 8.143E-18 \\ \hline - Th228 & & 8.475E-12 & & 1.004E-10 \\ \hline - Th229 & & 2.727E-12 & & 4.065E-12 \\ \hline - Th230 & & 2.625E-09 & & 2.139E-09 \\ \hline - Th232 & & 4.174E-10 & & 4.425E-11 \\ \hline - Bi209 & & 6.607E-16 & & 2.600E-14 \\ \hline - Ac227 & & 3.096E-14 & & 4.840E-15 \\ \hline - Pa231 & & 9.246E-10 & & 1.300E-10 \\ \hline - U232 & & 0.000 & & 0.000 \\ \hline - U233 & & 2.213E-09 & & 5.528E-09 \\ \hline - U234 & 0.000& 0.000 & & 0.000 \\ \hline - U235 & 0.032& 0.007 & 0.002 & 0.000 \\ \hline - U236 & & 0.005 & & 0.000 \\ \hline - U238 & 0.968& 0.920 & 0.887 & 0.808 \\ \hline - Np237 & & 0.000 & & 0.000 \\ \hline - Pu238 & & 0.000 & 0.001 & 0.001 \\ \hline - Pu239 & & 0.006 & 0.060 & 0.085 \\ \hline - Pu240 & & 0.002 & 0.027 & 0.027 \\ \hline - Pu241 & & 0.001 & 0.014 & 0.003 \\ \hline - Pu242 & & 0.000 & 0.005 & 0.001 \\ \hline - Pu244 & & 2.864E-08 & 1.508E-07 & 5.461E-09 \\ \hline - Am241 & & 6.442E-05 & & 0.001 \\ \hline - Am242m & & 8.533E-07 & & 7.961E-05 \\ \hline - Am243 & & 0.000 & & 0.000 \\ \hline - Cm242 & & 2.589E-05 & & 5.331E-05 \\ \hline - Cm243 & & 0.000 & & 3.242E-06 \\ \hline - Cm244 & & 8.561E-05 & & 0.000 \\ \hline - Cm245 & & 5.721E-06 & & 3.936E-05 \\ \hline - Cm246 & & 7.295E-07 & & 1.434E-05 \\ \hline - Cm247 & & 0.000 & & 5.317E-07 \\ \hline - Cm248 & & 7.691E-10 & & 0.000 \\ \hline - Cm250 & & 4.280E-18 & & 6.407E-15 \\ \hline - Cf249 & & 1.649E-12 & & 6.446E-10 \\ \hline - Cf250 & & 2.041E-12 & & 6.703E-11 \\ \hline - Cf251 & & 9.865E-13 & & 1.903E-12 \\ \hline - Cf 252 & & 6.579E-13 & & 4.014E-14 \\ \hline - H3 & & 8.584E-08 & & 1.747E-07 \\ \hline - C14 & & 4.057E-11 & & \\ \hline - C Other & & & & \\ \hline - Kr81 & & 4.216E-11 & & 8.038E-12 \\ \hline - Kr85 & & 3.444E-05 & & 2.950E-05 \\ \hline - Kr Other & & 0.000 & & 0.000 \\ \hline - Sr90 & & 0.001 & & 0.001 \\ \hline - Sr Other & & 0.000 & & 0.000 \\ \hline - Tc99 & & 0.000 & & 5.391E-05 \\ \hline - Tc Other & & 0.000 & & 0.002 \\ \hline - - \end{tabular}} - \caption{Fresh and Spent Fuel Compositions} - \label{tab:comp} -\end {table} -\end{frame} - %tikz styling definitions \tikzstyle{decision} = [diamond, draw, fill=blue!20, @@ -105,7 +38,7 @@ \subsection{Assumptions} \tikzstyle{cloud} = [draw, ellipse,fill=red!20, node distance=3cm, minimum height=2em] -\subsection{Simulation Specifications} +\subsection{Simulation Parameters} \begin{frame} \frametitle{Material Flow} @@ -178,19 +111,20 @@ \subsection{Simulation Specifications} \centering \begin{tabularx}{\textwidth}{bb} \hline - Specification & Value \\ + Parameter & Value \\ \hline - Simulation Time & 1970-2050 \\ - Reprocessing Capacity & 91.6 MTHM of \gls{UNF} per month \cite{schneider_spent_2008} \\ - Reprocessing Efficiency & 99.8\% \\ - Reprocessing Streams & Plutonium and Uranium \\ + Simulation Start Year & 1970 \\ + Simulation End Year & 2050 \\ + Reprocessing Capacity & 91.6 [MTHM \gls{UNF} per month] \cite{schneider_spent_2008} \\ + Reprocessing Efficiency & 99.8 [\%] \\ + Reprocessing Streams & Plutonium and Uranium \\ \gls{MOX} Fabrication & \small{9\% Reprocessed Pu + 91\% Depleted U} \\ - \gls{MOX} Fabrication Throughput & 16.25 MTHM of \gls{MOX} per month \cite{hugelmann_melox_1999} \\ + \gls{MOX} Fabrication Throughput & 16.25 [MTHM of \gls{MOX} per month] \cite{hugelmann_melox_1999} \\ \gls{MOX} Fuel Reprocessing Stage & Used \gls{MOX} gets reprocessed infinitely. \\ Reprocessed Uranium Usage & None. Stockpile reprocessed U \\ \hline \end{tabularx} - \caption {Specification for Historical Operation of \gls{EU} Case} + \caption {Parameter for Historical Operation of \gls{EU} Case} \label{tab:sim_eu} \end{table} @@ -203,7 +137,7 @@ \subsection{Simulation Specifications} \centering \begin{tabularx}{\textwidth}{bb} \hline - Specification & Value \\ + Parameter & Value \\ \hline Simulation Time & 1970-2160 \\ \gls{SFR} Available Year & 2040 \\ @@ -214,12 +148,12 @@ \subsection{Simulation Specifications} \small{Used \gls{UOX} and Depleted U Inventory} & 141,659 MTHM {\small (From first simulation)} \\ \small{Additional Used \gls{UOX} or Depleted U} & None \\ \gls{MOX} Fabrication & \small{11\% Reprocessed Pu + 89\% Depleted U} \\ - \gls{MOX} Fabrication Throughput & infinite \\ + \gls{MOX} Fabrication Throughput & $\infty$ \\ \gls{MOX} Fuel Reprocessing Stage & Used \gls{MOX} gets reprocessed infinitely. \\ Reprocessed Uranium Usage & None. Stockpile reprocessed U. \\ \hline \end{tabularx} - \caption {Specification for French Transition to \gls{SFR} case } + \caption {Parameter for French Transition to \gls{SFR} case } \label{tab:sim_france} \end{table} @@ -227,57 +161,37 @@ \subsection{Simulation Specifications} \begin{frame} - \frametitle{Reactor Specifications - PWR} + \frametitle{Reactor Parameters - \glspl{LWR} } \begin{table}[h] - \centering - \begin{tabularx}{\textwidth}{bb} - \hline - Specification & Value \\ - \hline - PWR Cycle Time & 18 months \\ - PWR Refueling Outage & 2 months \\ - Fuel Mass per Assembly & 523.4 kg \\ - Burnup & 51 GWd/tons \\ - Num. of Aseem. per Core & 193 for 1,000 MWe, linearly adjusted\\ - Num. of Assem. per Batch & 1/3 of the core \\ - Fuel & \small{French \glspl{PWR} prefer \gls{MOX} but also accept \gls{UOX}}\\ - \hline - \end{tabularx} - \caption {\gls{PWR} Specifications} - \label{tab:pwr} - \end{table} + \centering + \begin{tabularx}{\textwidth}{bbbb} + \hline + Parameter & Units & PWR & BWR \\ + \hline + cycle time & months & 18 & 18 \\ + refueling outage & months & 2 & 2 \\ + Fuel mass per assembly & kg & 523.4 & 180 \\ + Burnup & GWd/MTHM & 51 & 51 \\ + Num. of assem. per core & & 193 for 1,000 MWe, linearly adjusted & 764 for 1,000 MWe, linearly adjusted \\ + Num. of assem. per batch & 62 for 1,000 MWe, linearly adjusted & 127 for 1,000 MWe, linearly adjusted \\ + Fuel & \small{French \glspl{PWR} prefer \gls{MOX} but also accept \gls{UOX}} & 3\% enriched \gls{UOX} \\ + \hline + \end{tabularx} + \caption {\gls{LWR} Parameters} + \label{tab:lwr} + \end{table} \end{frame} -\begin{frame} - \frametitle{Reactor Specifications - BWR} - \begin{table}[h] - \centering - \begin{tabularx}{\textwidth}{bb} - \hline - Specification & Value \\ - \hline - BWR Cycle Time & 18 months \\ - PWR Refueling Outage & 2 months \\ - Fuel Mass per Assembly & 180 kg \\ - Burnup & 51 GWd/tons \\ - Num. of Aseem. per Core & 764 for 1,000 MWe, linearly adjusted\\ - Num. of Assem. per Batch & 1/3 of the core \\ - \hline - \end{tabularx} - \caption {\gls{BWR} Specifications} - \label{tab:bwr} -\end{table} -\end{frame} \begin{frame} - \frametitle{Reactor Specifications - ASTRID-type SFRs} + \frametitle{Reactor Parameters - ASTRID-type SFRs} \begin{table}[h] \centering \begin{tabularx}{\textwidth}{bb} \hline - Specification & Value \\ + Parameter & Value \\ \hline SFR Cycle Time & 12 months \\ SFR Refueling Outage & 2 months \\ @@ -288,7 +202,7 @@ \subsection{Simulation Specifications} Fuel & {\small \gls{MOX} (89\% Tailings, 11\% Separated Pu)}\\ \hline \end{tabularx} - \caption {\gls{SFR} ASTRID Specifications \cite{marsaultmarie-sophie_pre-conceptual_2012}} + \caption {\gls{SFR} ASTRID Parameters \cite{marsaultmarie-sophie_pre-conceptual_2012}} \label{tab:sfr} \end{table} \end{frame} diff --git a/conclusion.tex b/conclusion.tex index 56b4c53..9126380 100644 --- a/conclusion.tex +++ b/conclusion.tex @@ -1,6 +1,6 @@ \begin{frame} \frametitle{Conclusion} - France can transition into, for unchanging nuclear electricity demand, + France can transition into a fully SFR fleet with installed capacity of 66GWe by 2076. \begin{itemize} \item Reprocessing Capacity : $\approx 250 \frac{MTHM}{month}$ @@ -12,7 +12,7 @@ \frametitle{Discussion} \begin{itemize} \item Most EU nations do not have an operating repository or management plan - \item Some nations need a repository for complete decommission \& Nuclear phase-out + \item Some nations need a repository for complete decommission \& nuclear phase-out \item Strong incentive for collaboration \end{itemize} \end{frame} \ No newline at end of file diff --git a/future.tex b/future.tex index f1996ce..d6ed887 100644 --- a/future.tex +++ b/future.tex @@ -1,8 +1,10 @@ \subsection{Future Projections} \begin{frame} - \frametitle{Future Nuclear Projections} - From the World Nuclear Association \cite{world_nuclear_association_nuclear_2017}. + \frametitle{Future Deployment of Reactors in \gls{EU}} + The power reactors listed in the table are used in the simulation + to predict \gls{EU} \gls{UNF} inventory in 2050. The table is from + the World Nuclear Association \cite{world_nuclear_association_nuclear_2017}. \begin{table}[h] \centering \caption {Power Reactors under construction and planned \cite{world_nuclear_association_nuclear_2017}} @@ -37,7 +39,7 @@ \subsection{Future Projections} \begin{frame} - \frametitle{Nuclear Projection by Nation} + \frametitle{Simulated European Deployment} \begin{table}[h] \centering diff --git a/results.tex b/results.tex index 0185648..3bd3300 100644 --- a/results.tex +++ b/results.tex @@ -1,4 +1,4 @@ -\subsection{EU Nuclear Operation ~2050} +\subsection{EU Nuclear Operation until 2050} \begin{frame} \frametitle{Historical Operation of EU Reactors} @@ -8,13 +8,13 @@ \subsection{EU Nuclear Operation ~2050} % \scalebox{0.86}{ \begin{tabular}{|c|c|c|c|} \hline - Category & Unit & Value & Specifics\\ \hline - Total UOX Usage & MTHM & 181,471 & \\ \hline - Total MOX Usage & MTHM & 6,302 & \\ \hline - Total Used UOX Stored & MTHM & 141,659 & \gls{UNF} that is not reprocessed\\ \hline - Total Used MOX Stored & MTHM & 3,611 & \gls{UNF} that is not reprocessed \\ \hline - Total Tailings & MTHM & 1,081,826 & \\ \hline - Total Natural U Used & MTHM & 1,269,897 & \\ \hline + Category & Value & Unit & Specifics\\ \hline + Total UOX Usage & 181,471 & MTHM & \\ \hline + Total MOX Usage & 6,302 & MTHM & \\ \hline + Total Used UOX Stored & 141,659 & MTHM & \gls{UNF} that is not reprocessed\\ \hline + Total Used MOX Stored & 3,611 & MTHM & \gls{UNF} that is not reprocessed \\ \hline + Total Tailings & 1,081,826 & MTHM & \\ \hline + Total Natural U Used & 1,269,897 & MTHM & \\ \hline \end{tabular} \caption{Simulation Results for Historical Nuclear Operation of \gls{EU} Nations} \label{tab:sim_result} @@ -23,7 +23,7 @@ \subsection{EU Nuclear Operation ~2050} \end{frame} \begin{frame} - \frametitle{ Tails and UNF Inventory} + \frametitle{Tails and UNF Inventory} \begin{figure}[htbp!] \begin{minipage}[b]{.45\linewidth} \begin{center}