diff --git a/se_sensitivity/se_sensitivity_paper.tex b/se_sensitivity/se_sensitivity_paper.tex index 494f73c..d537120 100644 --- a/se_sensitivity/se_sensitivity_paper.tex +++ b/se_sensitivity/se_sensitivity_paper.tex @@ -90,7 +90,7 @@ \subsection{Overview of Methods} the LWR, for instance burnup and spent fuel isotopic composition, are the reference values adopted in a recent OECD Nuclear Energy Agency (NEA) systems study \cite{NEA-5990}. The fuel cycle material balance strategy for FR -multirecycle is identical to that used in both the OECD and the AFC R\&D +multi-recycle is identical to that used in both the OECD and the AFC R\&D studies: to reach the designated burnup level, the first core of the FR is loaded with only DU and retrieved TRU from LWR UF. The second and subsequent cycle are loaded with TRU and U from FR UF plus retrieved @@ -146,7 +146,7 @@ \subsection{System Performance Assessment} \mbox{FCC}_t = C_u \cdot s \end{equation} where $C_u$ [\$/KgHM or \$/SWU] is the unit charge and $s$ [kgHM/yr or SWU/yr] -is the service ammount. The FCC [\$/MWh] may then be obtained by dividing the +is the service amount. The FCC [\$/MWh] may then be obtained by dividing the FCC\subscript{t} total charge [\$/yr] by the annual electricity production [MWh/yr]. A fuzzy logic based barrier method is used to evaluate the @@ -181,7 +181,7 @@ \subsection{System Performance Assessment} 8 & DoseRate & mrem/hr/kg & Dose rate at 1-meter distance\\ 9 & Concentration & \# of CM/kg & Concentration of fissile material\\ 10 & Detectability & & Detectability levels (Five levels)\\ -11 & FacilityModTime & weeks & Modification timeto produce 1 CM in a year\\ +11 & FacilityModTime & weeks & Modification time to produce 1 CM in a year\\ 12 & AccessFrequency & days/yr & Frequency of possible access to facility\\ 13 & AvailableMass & \# of CM & Available fissile materials\\ 14 & MeasureUncert & \# of CM/yr & Uncertainty of measurement\\ @@ -305,7 +305,7 @@ \subsection{Benchmark Cases} \label{ses_table4} \begin{tabular}{|l|c|c|} \hline -\textbf{Nuclide} & \textbf{PWR Fresh} & \textbf{PWR UF} \\ +\textbf{Nuclide} & \textbf{LWR Fresh} & \textbf{LWR UF} \\ \hline \nuc{Am}{241} & & 4.74E-04\\ \nuc{Am}{243} & & 2.13E-04\\ @@ -345,8 +345,8 @@ \subsection{Benchmark Cases} \begin{center} \caption{Scheme 3a System and Reactor Design: 0.71\% NU is enriched to 4.20\% for UOX with tail enrichment -0.25\%; capacity of the PWR is 1450 MWe. The load factor is 90\%. The -burnup is 50 MWd/kgIHM for PWR and the UF is decayed for 6 years +0.25\%; capacity of the LWR is 1450 MWe. The load factor is 90\%. The +burnup is 50 MWd/kgIHM for LWR and the UF is decayed for 6 years before it is reprocessed. The retrieved TRU is mixed with DU for FR fresh fuel. The FR burnup is 140 MWd/kgIHM and the FR UF is reprocessed after 3 years of decay. The capacity of the FR is 600 MWe and the @@ -436,7 +436,7 @@ \subsection{Benchmark Results} does provide the TRU isotopics that serve as the starting point for the calculations carried out by the tool. The procedure described in \S \ref{1g_paper} was used to perform cycle iterations until the FR fuel -composition converged to equilibrium. Good agreement on the PWR to FR +composition converged to equilibrium. Good agreement on the LWR to FR power split, charge and discharge inventories and the FCC for scheme 3a can be observed. Whether the difference observed for scheme 3a can be ascribed to the FR simulation tool, or to inconsistencies in the LWR @@ -481,7 +481,7 @@ \subsection{Benchmark Results} \hline \textbf{Parameter} & \textbf{OECD 2006} & \textbf{Results} & \textbf{\% Difference} \\ \hline -Electricity Share: PWR [\%] & 63.2 & 66.1 & 4.59 \\ +Electricity Share: LWR [\%] & 63.2 & 66.1 & 4.59 \\ Electricity Share: FR [\% ] & 36.8 & 33.9 & -7.88 \\ \hline UOX FF [kg/TWh\subscript{e}] & 1513 & 1583 & 4.63 \\ @@ -704,7 +704,7 @@ \subsubsection{Material Balance and Isotopics} streams converges quickly toward an apparent equilibrium after only a few cycles. The criterion described in Table \ref{ses_table11} leads to equilibrium being reached at cycle 10. Therefore Figure \ref{ses_fig06} is very similar to the -cooresponding Figure \ref{1g_fig18} in \S \ref{1g_paper}. +corresponding Figure \ref{1g_fig18} in \S \ref{1g_paper}. \begin{figure}[htbp] \caption{Input Streams to FR Fuel Fabrication [kg/kgIHM]} @@ -1066,13 +1066,13 @@ \section{Conclusions} recalculates the transient and equilibrium FR cycle material balances. This new framework was applied to an AFC R\&D-inspired LWR and transmuter -FR fuel cycle architechture. Partitioning strategies were varied with +FR fuel cycle architecture. Partitioning strategies were varied with Np, Am/Cm, and Cs/Sr alternatively being partitioned for recycle or storage or sent to the repository with the low heat emitting fission products. -Elemental separation efficinecies were also varied with values of +Elemental separation efficiencies were also varied with values of 90\% to 99.99\% being considered. It was shown that the efficiency -of repository space usage, meausred by the energy produced by the fuel from -which the HLW placed in the repository was derived, can be imporved by +of repository space usage, measured by the energy produced by the fuel from +which the HLW placed in the repository was derived, can be improved by more than two orders of magnitude if 99.99\% separation efficiency is achieved and Cs/Sr are partitioned. If Cs/Sr are not partitioned, it was not seen to be worthwhile to exceed 99.9\% efficiency. On the other hand, @@ -1095,6 +1095,6 @@ \section{Conclusions} incorporates needed feedbacks between components. As such, a stochastic system wrapper that invokes this new fuel cycle tool could efficiently search the parameter space. This wrapper would be capable of generating -a large number of histories such that an information-theortic approach +a large number of histories such that an information-theoretic approach would also be needed to extract the relevant analyses from the data set.