\documentstyle[12pt,twoside,aries]{report} \begin{document} \newcommand{\AI}{\hbox{ARIES-I}} \newcommand{\VCT}{\hbox{V-15Cr-5Ti}} \newcommand{\HT}{\hbox{HT-9}} \newcommand{\degC}{$^\circ$C} \newcommand{\SdegC}{$\,^\circ$C} \newcommand{\SPL}{MgAl$_2$O$_4$} \newcommand{\AlO}{Al$_2$O$_3$} \newcommand{\LNO}{LiNO$_3$} \newcommand{\Z}{\phantom{0}} \newcommand{\D}{\phantom{.0}} \newcommand{\Y}{\phantom{$\sim$ }} \newcommand{\X}{\times} \newcommand{\Dtf}{\hbox{$\Delta T_f$}} \newcommand{\Dtw}{\hbox{$\Delta T_w$}} \newcommand{\M}{\multispan2} \newcommand{\B}[2]{\hbox to 0.6truein{\hfil #1 \hfil} \quad \hbox to 0.6truein {\hfil #2 \hfil}} \newcommand{\BB}[1]{\hbox to 1.3truein{\hfil #1 \hfil}} \newcommand{\MM}[1]{\multispan2{\hfil\hbox to 2.2truein{#1\hfil}}} % % RESET HEADING STYLE FOR APPENDIX % \renewcommand{\thechapter}{A} \renewcommand{\leftmark}{APPENDIX} \title{\bf APPENDIX} \author{ } \date{ } \maketitle \begin{titlepage} { \tableofcontents } \end{titlepage} \setcounter{page}{1} % % 1) CHAPTER TITLE IS NOT GIVEN WITH \CHAPTER SO THAT IT DOES NOT SAY % A. APPENDIX A % 2) HAS TO SET \thispagestyle{plain}, SO THAT PAGE HEADINGS DO NOT % APPEAR ON THE FIRST PAGE. % 3) SECTION TITLE IS CENTERED. % 4) ADDED EXTRA SPACE AFTER SECTION TITLE. % 5) STEPS 3 AND 4 SHOULD BE REPEATED FOR ALL SECTIONS. % \thispagestyle{plain} \date{ } \begin{center} {\Large \bf APPENDIX} \vskip 40pt \section{TABLE OF ARIES-I REACTOR PARAMETERS} \end{center} \vspace{20pt} % % 1) TABLE IN FOOTNOTESIZE. % 2) TABLE BROKEN INTO MANY TABLES, EACH ONE PAGE LONG, SO THAT TEX % CAPACITY WOULD NOT EXCEED AND ALSO PAGE BREAKING WOULD BE EASY. % 3) THE FIRST LINE IN EACH TABLE IS SET TO MAKE SURE THAT ALL TABLE HAVE % THE SAME ALIGNMENT. % %{\small { % \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr \cr \cr {\bf 1.} & \M{{\bf CHARACTERISTIC MACHINE DIMENSIONS \hfil}} & & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 1.1. & \M{Reactor Envelope$^{(a)}$ \hfil} & & \cr & 1.1.1. & Height & 14 & m \cr & 1.1.2. & Outside diameter & 24 & m \cr & 1.1.3. & Circumference & 74 & m \cr & 1.1.4. & Volume & 6,114 & m$^3$ \cr \cr 1.2. & \M{Plasma Chamber \hfil} & & \cr & 1.2.1. & Major toroidal radius & 6.75 & m \cr & 1.2.2. & Plasma half width & 1.50 & m \cr & 1.2.3. & First-wall half width & 1.60 & m \cr & 1.2.4. & Plasma volume & 489 & m$^3$ \cr & 1.2.5. & Plasma chamber volume & 554 & m$^3$ \cr & 1.2.6. & Wall surface area & 619 & m$^2$ \cr & 1.2.7. & Number of sectors$^{(b)}$ & 16 & \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr {\bf 2.} & \M{{\bf PLASMA PARAMETERS$^{\bf (c)}$} \hfil} & & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 2.1. & \M{Fuel Cycle \hfil} & DT/Li & \cr \cr 2.2. & \M{Plasma Dimensions \hfil} \cr & 2.2.1. & Plasma aspect ratio & 4.50 & \cr & 2.2.2. & Major toroidal radius & 6.75 & m \cr & 2.2.3. & Plasma half width \cr & & 2.2.3.1.~~95\% flux surface & 1.45 & m \cr & & 2.2.3.2.~~Separatrix & 1.50 & m \cr & 2.2.4. & Plasma vertical elongation, $\kappa$ \cr & & 2.2.4.1.~~95\% flux surface & 1.60 & \cr & & 2.2.4.2.~~Separatrix & 1.80 & \cr & 2.2.5. & Plasma triangularity, $\delta$ \cr & & 2.2.5.1.~~95\% flux surface & 0.47 & \cr & & 2.2.5.2.~~Separatrix & 0.70 & \cr & 2.2.6. & Plasma volume \cr & & 2.2.6.1.~~95\% flux surface & 426 & m$^3$ \cr & & 2.2.6.2.~~Separatrix & 489 & m$^3$ \cr \cr 2.3. & \M{Electron Density$^{(d)}$ \hfil} \cr & 2.3.1. & Average & $1.45\X 10^{20}$ & m$^{-3}$ \cr & 2.3.2. & Peak & $1.89\X 10^{20}$ & m$^{-3}$ \cr & 2.3.3. & At separatrix & $1.00\X 10^{20}$ & m$^{-3}$ \cr \cr 2.4. & \M{Total Ion Density$^{(d)}$ \hfil} \cr & 2.4.1. & Average & $1.24\X 10^{20}$ & m$^{-3}$ \cr & 2.4.2. & Peak & $1.61\X 10^{20}$ & m$^{-3}$ \cr & 2.4.3. & At separatrix & $0.87\X 10^{20}$ & m$^{-3}$ \cr & 2.4.4. & Ion fractions & & \cr & & 2.4.4.1.~~Proton & 0.0004 & \cr & & 2.4.4.2.~~Deuterium & 0.4435 & \cr & & 2.4.4.3.~~Tritium & 0.4435 & \cr & & 2.4.4.4.~~$^3$He & 0.0026 & \cr & & 2.4.4.5.~~$^4$He & 0.1000 & \cr & & 2.4.4.6.~~Oxygen (impurity) & 0.0100 & \cr \cr 2.5. & \M{Electron Temperature$^{(d)}$ \hfil} & & \cr & 2.5.1. & Average (density weighted) & 19.3 & keV \cr & 2.5.2. & Average & 17.4 & keV \cr & 2.5.3. & Peak & 36.6 & keV \cr & 2.5.4. & Separatrix & 0.22 & keV \cr \cr 2.6. & \M{Ion Temperature$^{(d)}$ \hfil} & & \cr & 2.6.1. & Average (density weighted) & 20.0 & keV \cr & 2.6.2. & Average & 18.1 & keV \cr & 2.6.3. & Peak & 38.0 & keV \cr & 2.6.4. & Separatrix & 0.30 & keV \cr \cr 2.7. & \M{Effective Plasma Ion Charge \hfil} & 1.65 & \cr \cr 2.8. & \M{Core-Plasma Confinement \hfil} & & \cr & 2.8.1. & Particle confinement time $^{(e)}$ & 10.0 & s \cr & 2.8.2. & Lawson parameter & $2.94\X 10^{20}$ & s m$^{-3}$ \cr & 2.8.3. & Energy confinement time & 2.5 & s \cr & 2.8.4. & Confinement enhancement multiplier & & \cr & & 2.8.4.1.~~ITER89-P & 2.6 & \cr & & 2.8.4.2.~~Kaye-Goldston & 2.2 & \cr & 2.8.5. & Core-plasma radiation fraction & & \cr & & 2.8.5.1.~~Synchrotron & 0.402 & \cr & & 2.8.5.2.~~Bremsstrahlung & 0.093 & \cr & & 2.8.5.3.~~Impurity radiation & 0.005 & \cr & & 2.8.5.4.~~Total & 0.500 & \cr & 2.8.6. & Particle flux at separatrix & $1\X10^{19}$ &m$^{-2}$s$^{-1}$\cr & 2.8.7. & Heat flux at separatrix & 0.4 & MW/m$^{2}$\cr \cr 2.9. & \M{Plasma Toroidal Current \hfil} & 10.20 & MA \cr \cr 2.10. & \M{Plasma Toroidal Current Density$^{(d)}$ \hfil} & & \cr & 2.10.1. & Average & 0.85 & MA/m$^2$ \cr & 2.10.2. & Peak & 2.56 & MA/m$^2$ \cr \cr 2.11. & \M{Poloidal Field at Plasma Edge \hfil} & 0.94 & T \cr \cr 2.12. & \M{Toroidal Field \hfil} & & \cr & 2.12.1. & At plasma axis & 11.3 & T \cr & 2.12.2. & Peak field on the coil & 21.0 & T \cr \cr 2.13. & \M{Vertical Field \hfil} & & \cr & 2.13.1. & At plasma axis & 0.79 & T \cr % & 2.13.2. & Decay index, $n$ & & \cr \cr 2.14. & \M{Poloidal Beta \hfil} & & \cr & 2.14.1. & Total & 2.813 & \cr & 2.14.2. & Fuel ions and electrons & 2.295 & \cr & 2.14.3 & Peak Shafranov & 6.939 & \cr & 2.14.4 & $\epsilon \beta_p$ & 0.625 & \cr \cr 2.15. & \M{Toroidal Beta \hfil} & & \cr & 2.15.1. & Total & 0.019 & \cr & 2.15.2. & Fuel ions and electrons & 0.016 & \cr & 2.15.3. & Fast particles & 0.003 & \cr & 2.15.4. & Troyon coefficient & 0.032 & T/A-m \cr & 2.15.5. & Engineering beta$^{(f)}$ & 0.006 & \cr \cr 2.16. & \M{Safety Factor \hfil} & & \cr & 2.16.1. & On axis, $q_o$ & 1.30 & \cr & 2.16.2. & At edge, $q_\psi$ & 4.75 & \cr & 2.16.3. & At edge, $q_\star$ & 3.91 & \cr \cr 2.17. & \M{Bootstrap-Current Fraction \hfil} & 0.68 & \cr \cr 2.18. & \M{Current Drive \hfil} & & \cr & 2.18.1. & Method & \B{\us{FWCD}}{\us{LHCD}} & \cr & 2.18.2. & Frequency & \B{141}{8,000} & MHz \cr & 2.18.3. & Input electric power & \B{134}{7} & MW \cr & 2.18.4. & Power to the plasma & \B{\Z97}{5} & MW \cr & 2.18.5. & Driven current & \BB{3.26} & MA \cr & 2.18.6. & Efficiency & \BB{0.032} & A/W \cr & 2.18.7. & Efficiency factor, $\gamma$ & \BB{$0.33\X 10^{20}$} & A/m$^2$-W\cr \cr 2.19. & \M{Plasma Heating-to-Ignition Method$^{(g)}$ \hfil} & ICRF & \cr \cr 2.20. & \M{Plasma Ohmic Dissipation \hfil} & 0.85 & MW \cr & 2.20.1. & Plasma loop voltage & 0.084 & V \cr \cr 2.21. & \M{Plasma Disruption \hfil} & & \cr & 2.21.1. & Stored plasma thermal energy & 618 & MJ \cr & 2.21.2. & Most affected component & Divertor & \cr & 2.21.3. & Thermal energy on the divertor & 420 & MJ \cr & 2.21.4. & Quench time & 0.3 & ms \cr & 2.21.5. & Average heat flux & 36.7 & MW/m$^2$\cr & 2.21.6. & Local peaking factor & 5 & \cr & 2.21.7. & Divertor armor disruption-allowance layer & 1 & mm \cr & 2.21.8. & \M{Divertor armor ablation thickness per disruption \hfil 100} & $\mu$m \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr {\bf 3.} & \M{{\bf POWER FLOW} \hfil} & & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 3.1. & \M{Total Nuclear Power ($M_NP_N +P_\alpha$)\hfil} & 2,387 & MW \cr & 3.1.1. & Fusion power & 1,925 & MW \cr & & 3.1.1.1.~~Charged-particle power, $P_\alpha$ & 386 & MW \cr & & 3.1.1.2.~~Neutron power, $P_N$ & 1,539 & MW \cr & 3.1.2. & Blanket energy multiplication, $M_N$ & 1.30 & \cr \cr 3.2. & \M{Total Plasma Power \hfil} & & \cr & 3.2.1. & Charged-particle power, $P_\alpha$ & 386 & MW \cr & 3.2.2. & Current-drive power & 102 & MW \cr & 3.2.3. & Bremsstrahlung & 49 & MW \cr & & 3.2.3.1.~~To first wall & 39 & MW \cr & & 3.2.3.2.~~To divertor & 10 & MW \cr & 3.2.4. & Synchrotron & 195 & MW \cr & & 3.2.4.1.~~To first wall & 173 & MW \cr & & 3.2.4.2.~~To divertor & 5 & MW \cr & & 3.2.4.3.~~To ``holes''$^{(h)}$ & 17 & MW \cr & 3.2.5. & Transport into scrape-off layer & 244 & MW \cr & & 3.2.5.1.~~Radiation in scrape-off layer & 0 & MW \cr & & 3.2.5.2.~~Radiation in divertor & 0 & MW \cr & & 3.2.5.3.~~Transport to first wall & 2 & MW \cr & & 3.2.5.4.~~Transport to divertor & 242 & MW \cr \cr 3.3. & \M{First-Wall Thermal Power \hfil} & 305 & MW \cr & 3.3.1. & Surface heating & & \cr & & 3.3.1.1.~~Radiation & 229 & MW \cr & & 3.3.1.2.~~Plasma & 2 & MW \cr & 3.3.2. & Nuclear heating & & \cr & & 3.3.2.1.~~Structure & 73 & MW \cr & & 3.3.2.2.~~Coolant & 0 & MW \cr & 3.3.3. & Coolant-pumping power & 1 & MW \cr \cr \cr \cr \cr \cr 3.4. & \M{Breeder/Multiplier-Zone Thermal Power \hfil} & 1,458 & MW \cr & 3.4.1. & Nuclear heating & & \cr & & 3.4.1.1.~~Structure & 235 & MW \cr & & 3.4.1.2.~~Coolant & 0 & MW \cr & & 3.4.1.3.~~Beryllium & 422 & MW \cr & & 3.4.1.4.~~Breeder & 789 & MW \cr & 3.4.2. & Coolant-pumping power & 12 & MW \cr \cr 3.5. & \M{Reflector-Zone Thermal Power \hfil} & 459 & MW \cr & 3.5.1. & Nuclear heating & & \cr & & 3.5.1.1.~~Structure & 453 & MW \cr & & 3.5.1.2.~~Coolant & 0 & MW \cr & 3.5.2. & Coolant-pumping power & 6 & MW \cr \cr 3.6. & \M{Shield Thermal Power \hfil} & 11 & MW \cr & 3.6.1. & Nuclear heating & & \cr & & 3.6.1.1.~~Structure & 11 & MW \cr & & 3.6.1.2.~~Coolant & 0 & MW \cr & 3.6.2. & Coolant-pumping power & $<$1 & MW \cr \cr 3.7. & \M{Divertor-Plate Thermal Power \hfil} & 311 & MW \cr & 3.7.1. & Surface heating & & \cr & & 3.7.1.1.~~Radiation & 15 & MW \cr & & 3.7.1.2.~~Plasma & 242 & MW \cr & 3.7.2. & Nuclear heating & & \cr & & 3.7.2.1.~~Structure & 19 & MW \cr & & 3.7.2.2.~~Coolant & 0 & MW \cr & 3.7.3. & Coolant-pumping power & 35 & MW \cr \cr 3.8. & \M{Total Reactor Thermal Power, $P_{th}$ \hfil} & 2,544 & MW \cr & 3.8.1. & First-wall thermal power & 305 & MW \cr & 3.8.2. & Breeder/multiplier-zone thermal power & 1,458 & MW \cr & 3.8.3. & Reflector-zone thermal power & 459 & MW \cr & 3.8.4. & Shield thermal power & 11 & MW \cr & 3.8.5. & Divertor-plate thermal power & 311 & MW \cr \cr 3.9. & \M{Thermal-Cycle Efficiency, $\eta_{TH}$ \hfil} & 0.49 & \cr \cr 3.10. & \M{Gross Electric Power, $P_{ET}$\hfil} & 1,247 & MW \cr \cr 3.11. & \M{Recirculating Power \hfil} & 247 & MW \cr & 3.11.1. & Current-drive system & 141 & MW \cr & 3.11.2. & Coolant-pumping power & 54 & MW \cr & 3.11.3. & Auxiliary power & 52 & MW \cr \cr 3.12. & \M{Net Electric Power \hfil} & 1,000 & MW \cr \cr 3.13. & \M{Recirculating-Power Fraction, $\epsilon$ \hfil} & 0.198 & \cr \cr 3.14. & \M{Engineering, $Q_E$ ($= 1/\epsilon$) \hfil} & 5.058 & \cr \cr 3.15. & \M{Plasma, $Q_p$ ($= P_F/P_{CD}$) \hfil} & 19.91 & \cr \cr 3.16. & \M{Net Plant Efficiency, $\eta_p = \eta_{TH} (1 - \epsilon)$ \hfil} & 0.393 & \cr \cr 3.17. & \M{Mass Power Density (MPD)\hfil} & 99 & kWe/tonne \cr \cr 3.18. & \M{Plasma Power Density, $P_F/V_p$ \hfil} & 3.94 & MW/m$^3$ \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr {\bf 4.} & \M{\bf REACTOR COOLANT SYSTEM \hfil} \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 4.1. & \M{First-Wall System \hfil} & \MM{SiC-composite$^{(i)}$ shell with} \cr & & & \MM{circular coolant channels$^{(j)}$} \cr & & & \MM{forming the front and sides} \cr & & & \MM{of the blanket module.} \cr & & & \cr & 4.1.1. & Coolant & Helium & \cr & 4.1.2. & Structural material & SiC composite & \cr & 4.1.3. & Shell thickness$^{(k)}$ & 12 & mm \cr & 4.1.4. & Coolant-channel inner diameter & 8 & mm \cr & 4.1.5. & Erosion allowance & 2 & mm \cr & 4.1.6. & Structure volume fraction & 0.67 & \cr & 4.1.7. & Coolant volume fraction & 0.33 & \cr & 4.1.8. & Void volume fraction & N/A & \cr & 4.1.9. & Structure volumetric heating & 27.1 & MW/m$^3$ \cr & 4.1.10. & Coolant volumetric heating & 0.0 & MW/m$^3$ \cr & 4.1.11. & Outlet temperature & 923 & K \cr & 4.1.12. & Inlet temperature & 623 & K \cr & 4.1.13. & Outlet pressure & 9.98 & MPa \cr & 4.1.14. & Inlet pressure & 10 & MPa \cr & 4.1.15. & Pressure drop & 0.02 & MPa \cr & 4.1.16. & Maximum primary stress & 33 & MPa \cr & 4.1.17. & Maximum secondary stress & 44 & MPa \cr & 4.1.18. & Maximum wall temperature & & \cr & & 4.1.18.1.~~SiC composite$^{(j)}$ & 1,233 & K \cr & & 4.1.18.2.~~SiC coating$^{(k)}$ & 1,311 & K \cr & 4.1.19. & Total coolant flow rate & 171 & kg/s \cr & 4.1.20. & Maximum coolant flow velocity& 39 & m/s \cr & 4.1.21. & Reynolds number, $Re$ & $7\X 10^4$ & \cr & 4.1.22. & Nusselt number, $Nu$ & 130 & \cr & 4.1.23. & Prandtl number, $Pr$ & 0.667 & \cr & 4.1.24. & Critical heat flux & N/A & \cr & 4.1.25. & Subcooling at exit & N/A & \cr \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr 4.2. & \M{Breeder/Multiplier-Zone System\hfil} & \MM{Alternating layers of} \cr & & & \MM{He-cooled SiC-composite} \cr & & & \MM{shells$^{(i,j)}$ and sphere-packed} \cr & & & \MM{breeder/multiplier mixture.$^{(l)}$} \cr & & & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr & 4.2.1. & Coolant & Helium & \cr & 4.2.2. & Structural material & SiC composite & \cr & 4.2.3. & Multiplier material & Beryllium & \cr & 4.2.4. & Breeder material & Lithium zirconate & \cr & 4.2.5. & Outboard module width at the first wall & 1.64 & m \cr & 4.2.6. & Zone radial dimension & 0.2 & m \cr & 4.2.7. & Coolant shell thickness & 7 & mm \cr & 4.2.8. & Coolant-channel inner diameter & 5 & mm \cr & 4.2.9. & Number of coolant shells & 10 & \cr & 4.2.10. & Minimum sphere-pack-zone thickness & 11 & mm \cr & 4.2.11. & Structure volume fraction & 0.25 & \cr & 4.2.12. & Coolant volume fraction & 0.05 & \cr & 4.2.13. & Multiplier volume fraction$^{(l)}$ & 0.56 & \cr & 4.2.14. & Breeder volume fraction$^{(l)}$ & 0.14 & \cr & 4.2.15. & Maximum structure volumetric heating & 25 & MW/m$^3$ \cr & 4.2.16. & Coolant volumetric heating & 0.0 & MW/m$^3$ \cr & 4.2.17. & Maximum breeder/Be volumetric heating & 29 & MW/m$^3$ \cr & 4.2.18. & Outlet temperature & 923 & K \cr & 4.2.19. & Inlet temperature & 623 & K \cr & 4.2.20. & Outlet pressure & 9.97 & MPa \cr & 4.2.21. & Inlet pressure & 10 & MPa \cr & 4.2.22. & Maximum pressure drop & 0.03 & MPa \cr & 4.2.23. & Maximum breeder/Be temperature & 938 & K \cr & 4.2.24. & Total coolant flow rate & 964 & kg/s \cr & 4.2.25. & Maximum coolant flow velocity & 20 & m/s \cr & 4.2.26. & Reynolds number, $Re$ & $1.26\X 10^4$ & \cr & 4.2.27. & Nusselt number, $Nu$ & 33 & \cr & 4.2.28. & Tritium purge-stream gas & Helium & \cr & 4.2.29. & Tritium purge-stream gas pressure & 0.1 & MPa \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr 4.3. & \M{Reflector-Zone System \hfil} & \MM{Alternating layers of} \cr & & & \MM{He-cooled SiC-composite} \cr & & & \MM{shells$^{(i,j)}$ and sphere-packed$^{(l)}$} \cr & & & \MM{reflector material.$^{(m)}$}\cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr & 4.3.1. & Coolant & Helium & \cr & 4.3.2. & Structural material & SiC composite & \cr & 4.3.3. & Reflector material & & \cr & & 4.3.3.1.~~First zone & Beryllium & \cr & & 4.3.3.2.~~Second zone & SiC & \cr & 4.3.4. & Module width at the first wall & 1.64 & m \cr & 4.3.5. & Outboard radial-zone dimension & & \cr & & 4.3.5.1.~~First zone & 0.10 & m \cr & & 4.3.5.2.~~Second zone & 0.37 & m \cr & 4.3.6. & Inboard radial-zone dimension & & \cr & & 4.3.6.1.~~First zone & 0.10 & m \cr & & 4.3.6.2.~~Second zone & 0.07 & m \cr & 4.3.7. & Coolant shell thickness & 7 & mm \cr & 4.3.8. & Coolant-channel inner diameter & 5 & mm \cr & 4.3.9. & Number of coolant shells & 2 & \cr & 4.3.10. & Minimum sphere-pack-zone thickness & 11 & mm \cr & 4.3.11. & Structure volume fraction & 0.25 & \cr & 4.3.12. & Coolant volume fraction$^{(m)}$ & & \cr & & 4.3.12.1.~~First zone & 0.05 & \cr & & 4.3.12.2.~~Second zone & 0.25 & \cr & 4.3.13. & Reflector volume fraction & & \cr & & 4.3.13.1.~~First zone (Be) & 0.70 & \cr & & 4.3.13.2.~~Second zone (SiC) & 0.50 & \cr & 4.3.14. & Structure volumetric heating & 5.4 & MW/m$^3$ \cr & 4.3.15. & Coolant volumetric heating & 0.0 & MW/m$^3$ \cr & 4.3.16. & Maximum Be volumetric heating & 24 & MW/m$^3$ \cr & 4.3.17. & Outlet temperature & 923 & K \cr & 4.3.18. & Inlet temperature & 623 & K \cr & 4.3.19. & Outlet pressure & 10 & MPa \cr & 4.3.20. & Inlet pressure & 10 & MPa \cr & 4.3.21. & Pressure drop & 0.005 & MPa \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr & 4.3.22. & Maximum Be temperature & 1,073 & K \cr & 4.3.23. & Total coolant flow rate & 290 & kg/s \cr & 4.3.24. & Maximum coolant flow velocity & 8 & m/s \cr & 4.3.25. & Reynolds number, $Re$ & 5$\X 10^3$ & \cr & 4.3.26. & Nusselt number, $Nu$ & 16 & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 4.4. & \M{Shield System \hfil} & \MM{Alternating layers of} \cr & & & \MM{He-cooled SiC-composite} \cr & & & \MM{shells$^{(i,j)}$ and} \cr & & & \MM{shield material.$^{(n)}$}\cr & & & \cr & 4.4.1. & Coolant & Helium & \cr & 4.4.2. & Structural material & SiC composite & \cr & 4.4.3. & Shield material & SiC/B$_4$C & \cr & 4.4.4. & Radial thickness & & \cr & & 4.4.4.1.~~Inboard & 0.7 & m \cr & & 4.4.4.2.~~Outboard & 0.8 & m \cr & 4.4.5. & Shield coolant-shell thickness & 7 & mm \cr & 4.4.6. & Coolant-channel inner diameter & 5 & mm \cr & 4.4.7. & Number of reflector coolant shells & 4 & \cr & 4.4.8. & Structure volume fraction & 0.05 & \cr & 4.4.9. & Shield-material volume fraction & 0.90 & \cr & 4.4.10. & Coolant volume fraction & 0.05 & \cr & 4.4.11. & Structure volumetric heating & 3.1 & MW/m$^3$ \cr & 4.4.12. & Coolant volumetric heating & 0.0 & MW/m$^3$ \cr & 4.4.13. & Outlet temperature & 923 & K \cr & 4.4.14. & Inlet temperature & 623 & K \cr & 4.4.15. & Outlet pressure & 10 & MPa \cr & 4.4.16. & Inlet pressure & 10 & MPa \cr & 4.4.17. & Pressure drop & 0.006 & MPa \cr & 4.4.18. & Maximum temperature & 1,000 & K \cr & 4.4.19. & Total coolant flow rate & 7 & kg/s \cr & 4.4.20. & Maximum coolant flow velocity & 9 & m/s \cr & 4.4.21. & Reynolds number, $Re$ & $6 \X 10^3$ & \cr & 4.4.22. & Nusselt number, $Nu$ & 16 & \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr 4.5. & \M{Divertor Plate System \hfil} & \MM{He-cooled SiC-composite} \cr & & & \MM{shell$^{(i,j)}$ with plasma-sprayed} \cr & & & \MM{tungsten armor.} \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr & 4.5.1. & Coolant & Helium & \cr & 4.5.2. & Structural material & SiC composite & \cr & 4.5.3. & Armor material & Tungsten & \cr & 4.5.4. & Coolant-tube outer diameter & 3.5 & mm \cr & 4.5.5. & Coolant-tube inner diameter & 2.5 & mm \cr & 4.5.6. & Armor thickness & 2 & mm \cr & 4.5.7. & Outlet temperature & 923 & K \cr & 4.5.8. & Inlet temperature & 623 & K \cr & 4.5.9. & Outlet pressure & 9 & MPa \cr & 4.5.10. & Inlet pressure & 10 & MPa \cr & 4.5.11. & Maximum primary stress & 35 & MPa \cr & 4.5.12. & Maximum secondary stress & 86 & MPa \cr & 4.5.13. & Maximum structure temperature & 902 & K \cr & 4.5.14. & Maximum armor temperature & 1,094 & K \cr & 4.5.15. & Total coolant flow rate & 198 & kg/s \cr & 4.5.16. & Maximum coolant flow velocity & 195 & m/s \cr \cr 4.6. & \M{Coolant-Circulator Type \hfil} & & \cr & 4.6.1. & First wall, blanket, and shield & Centrifugal pump & \cr & 4.6.2. & Divertor plate & Centrifugal pump & \cr \cr 4.7. & \M{Power Input to Each Circulator \hfil} & & \cr & 4.7.1. & First wall, blanket, and shield & 19 & MW \cr & 4.7.2. & Divertor plate & 35 & MW \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr {\bf 5.} & \M{{\bf SHIELD COOLANT SYSTEM} \hfil} & & \cr \cr 5.1. & \M{Hot-Shield Coolant$^{(o)}$ \hfil} & Helium & \cr \cr \cr {\bf 6.} & \M{{\bf INTERMEDIATE COOLANT SYSTEM} \hfil} & \cr \Z\D\D & \Z\D\D\Z\D & & & \cr 6.1. & \M{Secondary Coolant \hfil} & None & \cr \cr \cr {\bf 7.} & \M{{\bf POWER CONVERSION SYSTEM} \hfil} & & \cr \cr 7.1. & \M{Cycle Type \hfil} & Advanced Rankine & \cr \cr 7.2. & \M{Number of Turbine/Generator Sets \hfil} & 2 & \cr \cr 7.3. & \M{Turbine Arrangement \hfil} & Tandem & \cr \cr 7.4. & \M{Number of Re-Heats \hfil} & 2 & \cr \cr 7.5. & \M{Number of Regenerative Feedwater Heaters \hfil} & 9 & \cr \cr 7.6. & \M{Throttle Steam Pressure \hfil} & 31 & MPa \cr \cr 7.7. & \M{Condenser Back Pressure\hfil} & 6.7$\X 10^{-3}$ & MPa \cr \cr 7.8. & \M{Total Steam Flow Rate \hfil} & 892 & kg/s \cr \cr 7.9. & \M{Throttle Steam Temperature\hfil} & 873 & K \cr \cr 7.10. & \M{Steam Temperature After Each Reheat\hfil} & 873 & K \cr \cr 7.11. & \M{Feedwater Inlet Temperature \hfil} & 574 & K \cr \cr 7.12. & \M{Gross Cycle Efficiency \hfil} & 0.49 & \cr \cr 7.13. & \M{Gross Electric Output \hfil} & 1,247 & MW \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr {\bf 8.} & \M{{\bf REACTOR AUXILIARY SYSTEM} \hfil} & & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 8.1. & \M{Magnet Cooling System \hfil} & & \cr & 8.1.1. & Toroidal-field coils & & \cr & & 8.1.1.1.~~Coolant & Helium & \cr & & \M{8.1.1.2.~~Total cooling load during start-up \hfil 0.5} & MJ \cr & & \M{8.1.1.3.~~Total cooling load during disruption \hfil 2.0} & MJ \cr & 8.1.2. & Poloidal-field coils & & \cr & & 8.1.2.1.~~Coolant & Helium & \cr & & \M{8.1.2.2.~~Total cooling load during start-up \hfil 0.8} & MJ \cr & & \M{8.1.2.3.~~Total cooling load during disruption \hfil 1.0} & MJ \cr \cr 8.2. & \M{Vacuum-Pumping System \hfil} & & \cr & 8.2.1. & Vacuum and plasma-chamber pressures & & \cr & & 8.2.1.1.~~Base plasma-chamber pressure & 10$^{-5}$ & mtorr \cr & & 8.2.1.2.~~Divertor duct pressure & 20 & mtorr \cr & 8.2.2. & Temperature of neutral gas & 1,300 & K \cr & 8.2.3. & Plasma chamber volume & 554 & m$^3$ \cr & 8.2.4. & Vacuum chamber volume & 650 & m$^3$ \cr & 8.2.5. & Particle throughput & & \cr & & 8.2.5.1.~~DT & 6.3$\X 10^{21}$ & s$^{-1}$ \cr & & 8.2.5.2.~~Helium & 6.8$\X 10^{20}$ & s$^{-1}$ \cr & 8.2.6. & Conductance of the divertor duct & 250 & m$^3$/s \cr & 8.2.7. & Type of pumps & Turbo-molecular & \cr & 8.2.8. & Number of vacuum pumps & 16 & \cr & 8.2.9. & Helium-pumping speed (per pump) & 25 & m$^3$/s \cr \cr 8.3. & \M{Plasma-Fueling System \hfil} & & \cr & 8.3.1. & Type & Pellet & \cr & 8.3.2. & Fuel composition & H, D, T, DT & \cr & 8.3.3. & Fueling rates & 2,645 & kg/d \cr & 8.3.4. & Pellet diameter & 4 -- 6 & mm \cr & 8.3.5. & Pellet speed & 1 -- 5 & km/s \cr & 8.3.6. & Pellet injection frequency & 3 & s$^{-1}$ \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr 8.4. & \M{Blanket Tritium-Processing and Recovery System\hfil} & & \cr & 8.4.1. & Type & Purge gas recovery & \cr & 8.4.2. & Total tritium inventory & 0.015 & kg \cr & 8.4.3. & Tritium handling rate & 0.354 & kg/d \cr & 8.4.4. & Water processing rate & N/A & \cr & 8.4.5. & \M{Primary-coolant tritium concentration \hfil Negligible} & \cr & 8.4.6. & Blanket detritriation factor & N/A & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 8.5. & \M{Fast-Wave Current-Drive System\hfil} & & \cr & 8.5.1. & Type & Folded waveguide & \cr & & \M{8.5.1.1.~~Structural material$^{(i,j)}$ \hfil Cu-coated SiC composite} & \cr & & 8.5.1.2.~~Number of modules & 2 & \cr & & 8.5.1.3.~~Dimensions ($w \X h \X d$) & $3.8\X0.6\X0.8$ & m\cr & & 8.5.1.4.~~First-wall perforation & 0.65 & \% \cr & & 8.5.1.5.~~Power & 22.0 & MW/m$^2$\cr & 8.5.2. & Transmission system & Coax & \cr & & 8.5.2.1.~~Power (per coax) & 4.2 & MW \cr & & 8.5.2.2.~~Efficiency & 90 & \% \cr & 8.5.3. & Radio-frequency transmitter & Klystrode & \cr & & 8.5.3.1.~~Power (per unit) & 5 & MW \cr & & 8.5.3.2.~~Efficiency & 90 & \% \cr \cr 8.6. & \M{Auxiliary Plasma Heating$^{(g)}$\hfil} & & \cr & 8.6.1. & Type & ICRF & \cr & 9.4.2. & Frequency & 140 -- 170 & MHz \cr \cr 8.7. & \M{Energy Transfer and Storage System\hfil} & Not required \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr {\bf 9.} & \M{{\bf REACTOR COMPONENTS} \hfil} & & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 9.1. & \M{First Wall, Blanket, and Shield \hfil} & & \cr & 9.1.1. & Structural material & SiC composite & \cr & 9.1.2. & Breeding material & Lithium zirconate & \cr & 9.1.3. & Neutron multiplier material & Beryllium & \cr & 9.1.4. & Tritium breeding ratio (TBR) & & \cr & & 9.1.4.1.~~Beginning of life & 1.20 & \cr & & 9.1.4.2.~~End of life & 1.17 & \cr & 9.1.5. & Blanket energy multiplication & 1.3 & \cr & 9.1.6. & Number of modules & 16 & \cr & 9.1.7. & Weight of module & 181.6 & tonne \cr & & 9.1.7.1.~~First wall & 0.8 & tonne \cr & & 9.1.7.2.~~Inboard blanket & 15.3 & tonne \cr & & 9.1.7.3.~~Outboard blanket & 67.1 & tonne \cr & & 9.1.7.4.~~Inboard shield & 15.2 & tonne \cr & & 9.1.7.5.~~Outboard shield & 82.7 & tonne \cr & & 9.1.7.6.~~Divertor & 0.5 & tonne \cr & 9.1.8. & \M{Largest single component \hfil Outboard shield sub-module} & \cr & & 9.1.8.1.~~Weight & 41.4 & tonne \cr & & 9.1.8.2.~~Dimensions ($w \X h \X d$) & $4.3 \X 4 \X 0.8$ & m \cr & 9.1.9. & Lifetime$^{(p)}$ & 6 & y \cr \cr 9.2. & \M{Divertor \hfil} & & \cr & 9.2.1. & Type & Double-null, high recycle & \cr & 9.2.2. & Neutralizer plate & & \cr & & 9.2.2.1.~~Armor & Tungsten & \cr & & 9.2.2.2.~~Coolant tube & SiC composite & \cr & & 9.2.2.3.~~Coolant & Helium & \cr & 9.2.3. & Weight of divertor (per module) & 119 & kg \cr & 9.2.4. & Dimensions & & \cr & & 9.2.4.1.~~Inboard toroidal length & 1.05 & m \cr & & 9.2.4.2.~~Outboard toroidal length & 1.31 & m \cr & & 9.2.4.3.~~Radial length & 2.17 & m \cr & 9.2.5. & Lifetime$^{(q)}$ & 2 & y \cr \cr \cr 9.3. & \M{Magnets \hfil} & & \cr & 9.3.1. & Poloidal-field coils & & \cr & & 9.3.1.1.~~Type & Superconducting & \cr & & 9.3.1.2.~~Number & 12 & \cr & & 9.3.1.3.~~Conductor & Nb$_3$(Sn-Ti) & \cr & & 9.3.1.4.~~Structure & Incoloy 908 & \cr & & 9.3.1.5.~~Insulator & Organic & \cr & & 9.3.1.6.~~Coolant & Helium & \cr & & 9.3.1.7.~~Operating temperature & 4.4 & K \cr & & 9.3.1.8.~~Maximum stress in coil & 700 & MPa \cr & 9.3.2. & Toroidal-field coils & & \cr & & 9.3.2.1.~~Type & Superconducting & \cr & & 9.3.2.2.~~Number & 16 & \cr & & 9.3.2.3.~~Conductor & Nb$_3$(Sn-Ti), NbTi & \cr & & 9.3.2.4.~~Structure & Incoloy 908 & \cr & & 9.3.2.5.~~Insulator & Organic & \cr & & 9.3.2.6.~~Coolant & Helium & \cr & & 9.3.2.7.~~Operating temperature & 3 -- 8 & K \cr & & 9.3.2.8.~~Peak stress in coil & 800 & MPa \cr & & 9.3.2.9.~~Mean coil radius & 7.15 & m \cr & 9.3.3. & Maximum toroidal field & & \cr & & 9.3.3.1.~~At plasma axis & 11.3 & T \cr & & 9.3.3.2.~~At toroidal-field coil & 21.0 & T \cr & 9.3.4. & Total stored energy & & \cr & & 9.3.4.1.~~Poloidal-field system & 13 & GJ \cr & & 9.3.4.2.~~Toroidal-field system & 125 & GJ \cr & 9.3.5. & Largest single component & TF coil & \cr & & 9.3.5.1.~~Weight & 190 & tonne \cr & & 9.3.5.2.~~Dimensions ($h \X d$) & $1 \X 8$ & m \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr {\bf 10.} & \M{{\bf ELECTRICAL POWER REQUIREMENTS}\hfil} & & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 10.1. & \M{Maximum Power from Grid for Cold-Plasma Start-up \hfil} & 200 & MW \cr \cr 10.2. & \M{Auxiliary-Power Requirements (Normal Operation) \hfil} & & \cr & 10.2.1. & Electrical energy storage & & \cr & 10.2.2. & Toroidal-field coils & $\sim$ 0 & MW \cr & 10.2.3. & Divertor-field coils & $\sim$ 0 & MW \cr & 10.2.4. & Current drive & 141 & MW \cr & 10.2.5. & First-wall, blanket, shield, & & \cr & & and divertor-plate coolant circulators & 54 & MW \cr & 10.2.6. & Other auxiliary systems & 52 & MW \cr & 10.2.7. & Total & 247 & MW \cr \cr \cr {\bf 11.} & \M{{\bf BUILDINGS} \hfil} & & \cr \cr 11.1. & \M{Reactor Hall \hfil} & & \cr & 11.1.1. & Characteristic dimensions$^{(r)}$ & & \cr & & 11.1.1.1.~~Outside diameter & 52 & m \cr & & 11.1.1.2.~~Height & 35 & m \cr & 11.1.2. & Enclosed volume & 7.4$\X 10^4$ & m$^3$ \cr & 11.1.3. & Minimum wall thickness & 1 & m \cr & 11.1.4. & Internal pressure & 1 & atm \cr & 11.1.5. & Containment atmosphere & Air & \cr \cr 11.2. & \M{Turbine Building \hfil} & & \cr & 11.2.1. & Characteristic dimensions & & \cr & & 11.2.1.1.~~Length & 100 & m \cr & & 11.2.1.2.~~Width & 40 & m \cr & & 11.2.1.3.~~Height & 33 & m \cr & 11.2.2. & Total enclosed volume & 2.6$\X 10^5$& m$^3$ \cr \cr 11.3. & \M{Reactor Service Building \hfil} & & \cr & 11.3.1. & Characteristic dimensions$^{(s)}$ ($w \X h \X d$) & $15 \X 30 \X 25$ & m \cr } \clearpage \halign to\hsize{#\hfil\tabskip=0pt & #\hfil\tabskip=0pt & #\hfil\tabskip=1pt plus 15truecm & \hfill#\tabskip=5pt & #\hfil\tabskip=0pt \cr {\bf 12.} & \M{{\bf REACTOR SAFETY AND WASTE DISPOSAL} \hfil} & & \cr \Z\D\D & \Z\D\D\Z\D & & & \phantom{kWe/tonne} \cr 12.1. & \M{Radioactive Material Storage for Life of Plant \hfil} & & \cr & 12.1.1. & Total Class C & & \cr & & 12.1.1.1.~~Weight & 4,924 & tonne \cr & & 12.1.1.2.~~Volume & 1,357 & m$^3$ \cr \cr 12.2. & \M{Tritium Inventory \hfil} & & \cr & 12.2.1. & First wall & 6 & g \cr & 12.2.2. & Blanket & & \cr & & 12.2.1.1~~Beryllium & 640 & g \cr & & 12.2.1.2~~Multiplier & 1 & g \cr & 12.2.3. & Divertor & 10 & g \cr \cr 12.3. &\multispan3{Peak Temperature During a Loss-of-Coolant Accident (LOCA)$^{(t)}$\hfil} & \cr & 12.3.1. & First wall & 1,053 & K \cr & 12.3.2. & Divertor & 1,293 & K \cr \cr 12.4. & \M{Off-Site Doses$^{(u)}$ at 1 km \hfil} & & \cr & 12.4.1. & Zirconium$^{(v)}$ & 91 & rem \cr & 12.4.2. & Tungsten$^{(w)}$ & 11.2 & rem \cr & 12.4.3. & Tritium$^{(x)}$ & 6.4 & rem \cr & 12.4.4. & First wall and reflector & 21 & rem \cr & 12.4.5. & Total & 130 & rem \cr } \clearpage \begin{center} {\bf FOOTNOTES TO TABLE A.1} \end{center} \vskip 20pt \begin{itemize} \item[(a)] The reactor envelope is the cylinder that includes all of the poloidal-field coils. \item[(b)] The \AI\ fusion power core comprises 16 self-supporting, identical modules. Each module includes portions of the first wall, blanket, shield, and vacuum vessel, and one TF coil. Reactor maintenance is based on replacing an entire module. \item[(c)] All plasma parameters are at steady-state burn except as noted. \item[(d)] Self-consistent plasma profiles are used for all plasma engineering analyses. The plasma profiles are: \begin{eqnarray} n(r) & = & n(edge) + n(0) \left[ 1 - (r/r_p)^2 \right]^{\alpha_n} \: , \nonumber \\ T(r) & = & T(0) \left[ 1 - (r/r_p)^2 \right]^{\alpha_T} \: , \nonumber \\ j(r) & = & j(0) \left[ 1 - (r/r_p)^2 \right]^{\alpha_j} \: , \nonumber \end{eqnarray} with $n(edge)/n = 0.7, \alpha_n = 1.0, \alpha_T=1.1$, and $\alpha_j = 2.$ The density profile resembles a parabolic profile with \hbox{$\alpha_n = 0.3$} if the edge density is zero. \item[(e)] It is assumed that $\tau_p \simeq 4 \tau_E$. \item[(f)] The engineering beta is defined as the ratio of the average plasma pressure to the maximum field strength on the TF coils. \item[(g)] The current-drive system is used for auxiliary heating during start-up. \item[(h)] A 6\% ``hole'' fraction is assumed. The power into the ``hole'' (pumping ducts, waveguides) are assumed to be absorbed by the first-wall system. \item[(i)] The term ``SiC composite'' denotes an SiC-fiber-reinforced SiC-matrix material. The fabrication method consists of two major steps: (1) A preform of the component is woven or braided from continuous SiC fibers using numerically controlled weaving machines. (2) The fiber preform is chemical-vapor infiltrated (CVI) with SiC matrix material. A major advantage of these ceramic-composite manufacturing techniques is that the result is a near-net-shape component that requires only minimal finishing touches. Furthermore, external features such as attachment holes and flanges can be integrated into the preform weaving process. \item[(j)] The first-wall and blanket shells are in the form of tube-sheets. Each shell is woven as a complete unit by programming the weaving machine to serpentine SiC fibers from tube to tube. It should be noted that such a tube-sheet is structurally quite different from conventional metallic tube-sheets (during welding of metallic tube-sheets, the microstructure of the tube wall in the vicinity of the weld changes, which may result in weak spots). \item[(k)] A 2-mm thick, 100\%-dense SiC layer is chemical-vapor deposited (CVD) on the first-wall shell facing the plasma. This layer serves a double purpose: (1) It constitutes a sacrificial layer for erosion over the first-wall lifetime, and (2) it serves as a coolant leak barrier into the vacuum chamber. Among SiC ceramics, CVD SiC has one of the lowest hydrogen-diffusion coefficients at elevated temperatures (in the fission industry, a CVD layer of SiC is used to contain gaseous fission products inside spherical fission-reactor fuel elements). \item[(l)]The breeder/multiplier mixture is 20\% breeder (lithium zirconate) and 80\% Be with a theoretical density of 90\%. The sphere-pack pebbles have a binary mixture of spheres with diameters of 1 and 0.1 mm (a packing fraction of 80\%). \item[(m)]The reflector material is Be in the front zone and SiC in the rear zone, both with a theoretical density of 90\%. The sphere-pack pebbles have a binary mixture of spheres with diameters of 1 and 0.1 mm (a packing fraction of 80\%). The rear zone of the reflector includes the coolant plena for the first wall and blanket. \item[(n)] The shield materials are high-density SiC and B$_4$C. The shield also incorporates multiple layers of aluminum sheets sandwiched between He-cooled SiC shells to provide passive stabilization against vertical motion of the plasma. There are 40 layers of 1-mm-thick aluminum sheets and 40 layers of 19-mm-thick SiC shells for an overall shield thickness of 0.8~m. All of the aluminum sheets within a module are electrically connected together at the back of the shield. Neighboring shield modules are also electrically connected together with a detachable jumper to provide a complete toroidal circuit. Analysis shows that most of the electromagnetic forces generated by a plasma disruption appear on the aluminum sheets (since SiC composite is not electrically conducting) and, in effect, the aluminum shells shield the vacuum vessel from disruption forces. The disruption-induced electromagnetic forces generated in each of the aluminum sheets are restrained by the neighboring SiC shells. \item[(o)] Thermal power is recovered from the hot shield (see no.~4.4). \item[(p)] The SiC displacement-damage energy was estimated to be 25~eV. Based on this displacement damage energy, a displacement-per-atom (dpa) rate of 11 per MWy/m$^2$ was calculated. It has been suggested that radiation-damage-resistant metallic alloys may survive a total of 200~dpa. Because there are no data for SiC composite, the same maximum dpa value of 200 is adopted for the \hbox{ARIES-I} first wall, resulting in a lifetime of $\sim$18~MWy/m$^2$. Then, in \hbox{ARIES-I} with a peak neutron wall loading of 4~MW/m$^2$, the lifetime of the first wall would be 4.5 full power years (FPY) or 6 calendar years. More recent analytical damage calculations suggest that the damage energy for SiC could be as high as 4 times the value used for \AI. This would mean that the dpa rate would be lower by a factor of $\sim$4 and the first-wall lifetime would be $\sim$4 times longer. However, the predicted high resistance of SiC composite to displacement damage should be verified experimentally. \item[(q)] Because of extreme heat and particle fluxes on the divertor plate, its lifetime is assumed to be 2~FPY, considerably lower than its radiation-damage lifetime. \item[(r)] The reactor-hall building diameter is estimated at twice the reactor envelope diameter and its height is based on the vertical-lift maintenance scheme, which requires a clearance of at least 12~m. \item[(s)] Because the fusion power core is modular, the service building for the reactor can be small. \item[(t)] At the onset of a LOCA, the plasma is assumed to be quenched with a 10-s power ramp-down. \item[(u)] Off-site dose is calculated based on the radioactive inventory at the end of life for all components and using the following conditions: distance from release point is 1~km, CLASS-F stability, wind speed is 1~m/s, release duration is 3~m, Gaussian plume dimensions are \hbox{$\sigma_y = 100$~m} and \hbox{$\sigma_z = 50$~m}. \item[(v)] The zirconium is tailored to the following isotopic mixture: $^{90}$Zr (0.057\%), $^{91}$Zr (0.013\%), $^{92}$Zr (99.908\%), $^{94}$Zr (0.019\%), $^{96}$Zr (0.003\%). The cost of tailoring Zr is \$2097/kg using the ALVIS (atomic-vapor laser-isotope separation) technique at \$50/swu (standard weight units). \item[(w)] The 2-mm-thick tungsten layer of the divertor plate is tailored to the following isotopic mixture: $^{180}$W (0.02\%), $^{182}$W (3.23\%), $^{183}$W (90.00\%), $^{184}$W (3.76\%), $^{186}$W (3.51\%). \item[(x)] Assuming release of all of tritium inventory in the FPC. \end{itemize} } \clearpage \begin{center} \section{SYSTEMS-CODE PARAMETERS OF ARIES-I} \end{center} \vspace{20pt} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \begin{center} \section{COST SUMMARY OF ARIES-I REACTOR} \end{center} \vspace{20pt} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \begin{center} \section{COST DATA BASE FOR ARIES-I REACTOR} \end{center} \vspace{20pt} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \vspace*{1.in} \clearpage \begin{thebibliography}{99} \bibitem{SCH78} S.~C.~Schulte, T.~L.~Wilke, and J.~R.~Young, ``Fusion Reactor Design Studies---Standard Accounts for Cost Estimates,'' Battelle Pacific Northwest Laboratory report \hbox{PNL-2648} (1978). \bibitem{SCH79} S.~C.~Schulte, W.~E.~Bickford, C.~E.~Willingham, S.~K.~Ghose, and M.~G.~Walker, ``Fusion Reactor Design Studies---Standard Unit Costs and Cost Scaling Rules,'' Battelle Pacific Northwest Laboratory report \hbox{PNL-2987} (1979). \bibitem{PHU79} D.~L.~Phung, ``A Method for Estimating Escalation and Interest During Construction (EDC and IDC),'' in {\it Proc.\ 2nd Miami Conf.\ on Alternative Energy Sources} (Dec.~1979). \bibitem{HAM85} W.~R.~Hamilton, D.~C.~Keeton, and S.~L.~Thomson, 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