The FuTure oF nuclear Fuel cycle - MIT Energy Initiative

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Table of Contents Study Participants MIT nuclear Fuel cycle Study advisory committee Members Foreword and acknowledgments executive Summary Postscript iii iv vii ix xv chapter 1. The Future of the nuclear Fuel cycle— overview, conclusions, and recommendations 1 chapter 2. Framing Fuel cycle Questions 19 chapter 3. uranium resources 31 chapter 4. Interim Storage of Spent nuclear Fuel 43 chapter 5. Waste Management 55 chapter 6. analysis of Fuel cycle options 71 chapter 7. economics 99 chapter 8. Fuel cycles and nonproliferation 111 chapter 9. american attitudes about nuclear Power and nuclear Waste 127 chapter 10. recommended analysis, research, development, and demonstration Programs 133 appendiCeS appendix to chapter 3: uranium resource elasticity Model 143 appendix to chapter 5: Waste Management 155 appendix to chapter 7: economics 167 appendix a. Thorium Fuel cycle options 181 appendix B. advanced Technologies 191 appendix c. high-Temperature reactors with coated-Particle Fuel 207 appendix d. Intergenerational equity considerations of Fuel cycle choices 213 appendix e. Status of Fuel cycle Technologies 229 v
vi MIT STudy on The FuTure oF nuclear Fuel cycle
Page 3 and 4: Other Reports in This Series The Fu
Page 5: MIT Nuclear Fuel Cycle Study Adviso
Page 9 and 10: viii MIT STudy on The FuTure oF nuc
Page 11 and 12: Study Findings and Recommendations
Page 13 and 14: Recommendation We recommend that a
Page 15 and 16: p Innovative nuclear energy applica
Page 17 and 18: p In line with many of our R&D reco
Page 19 and 20: The “once through” or open fuel
Page 21 and 22: have been implemented slowly. This
Page 23 and 24: Recommendation We recommend that th
Page 25 and 26: oped policies for specific wastes r
Page 27 and 28: nuClear Fuel CyCleS The united Stat
Page 29 and 30: - The primary differences were in t
Page 31 and 32: Recommendation Integrated system st
Page 33 and 34: Table 1.2 Summary of R&D Recommenda
Page 35 and 36: 18 MIT STudy on The FuTure oF nucle
Page 37 and 38: the once-through Fuel Cycle for lig
Page 39 and 40: tricity costs. Waste management cos
Page 41 and 42: Figure 2.3 partial recycle of lWr S
Page 43 and 44: history of the nuclear Fuel Cycle B
Page 45 and 46: • What is the impact of timing of
Page 47 and 48: nuclear fuel cycles, the wastes (SN
Page 49 and 50: Because ore demand is closely coupl
Page 51 and 52: eStimatinG Future CoStS oF uranium
Page 53 and 54: Figure 3.3 relative uranium Cost vs
Page 55 and 56: Figure 3.4 100 year price trend for
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Stockpiling If supply interruption
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CitationS and noteS 1. Uranium 2007
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If SNF is to be shipped, typically
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a policy that maintains fuel cycle
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Dry cask storage is used for short
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For decommissioned sites, our econo
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with its attractiveness of jobs and
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54 MIT STudy on The FuTure oF nucle
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2. The United States should create
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Table 5.1 United States Waste Class
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table 5.3 examples of operational G
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Waste Isolation Pilot Plant The uni
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Successful repository programs are
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designed with limited SNF storage c
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CitationS and noteS 1. A Handbook f
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70 MIT STudy on The FuTure oF nucle
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energy spectrum centered at higher
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light Water reactor Fuel technical
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(fertile-free) to CR=1.0 (break-eve
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license. However, fuel reprocessing
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Figure 6.4 densification Factors as
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As expected, the breeder installed
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Figure 6.8 shows the development of
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Table 6.8 Uranium Cost in $/kg, Sta
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Figure 6.11 location of the tru inv
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SenSitivity analySiS: alternative a
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Fast reactor technical Characterist
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cooled fast reactor (SFR) fueled by
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Summary oF ConCluSionS Among the in
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[hoffman et al., 2006] e.a. hoffman
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This chapter reports the cost of th
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Table 7.1 Input Parameter Assumptio
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Twice-Through Cycle Table 7.3 shows
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Table 7.4 The LCOE for the Fast Rea
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higher cost of disposal of the spen
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110 MIT STudy on The FuTure oF nucl
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power program might be used, as is
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Figure 8.1 Weapons-usability Charac
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inStitutional approaCheS to Fuel Cy
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the iaea additional protocol an Iae
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in technology innovation are likely
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Reprocessing choices Commercial rep
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Table 8.2 Safeguard Technical Objec
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port for nuclear power over the per
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Those Americans who have an opinion
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who are very concerned with global
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p Waste management must be integrat
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options because we do not know toda
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Nuclear Security. Nonproliferation
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There have been major changes in ou
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There are large financial and polic
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Figure 3A.2 shows the results. As c
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Figure A.3 plots Eq (2), where adva
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Again, assuming that q = 0.29, the
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Note that Eq. [7] suggests employin
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Figure 3b.1 Cumulative probability
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Figure 5a.1 decay of radioactivity
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and 241 Am. For the short term, hea
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Repository Engineering All reposito
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epreSentative repoSitory deSiGnS: u
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orehole diSpoSal There are three me
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table 7a.1 list of variables , 1 lc
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The Twice-Through Cycle The LCOE fo
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A proper representation of the chai
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In the Twice-Through Cycle, the pai
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table 7a.2 once-through Fuel Cycle
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above ground storage. However, the
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CitationS and noteS 1. The methodol
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Historically, the interest in thori
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p Analogous to plutonium. Plutonium
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In case self-protection of U-232 da
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Figure a.3 Schematic view of Sbu an
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eaCtor teChnoloGieS Nuclear power e
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via 239 Pu and 240 Pu, and then the
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urnups, but the gap between the nec
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(~700°C) with higher thermal-to-el
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There are several unique consequenc
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performance goals can be achieved.
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is that it will be many decades bef
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system [1]. The nuclear power plant
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The HTRs can be used to provide hig
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[http://nextgenerationnuclearplant.
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CitationS and noteS Brinkmann, H. U
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The analysis is based on the assump
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considerations discussed above. We
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In our analysis we make the explici
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Figure d.4 transmutation Consequenc
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Figure d.5 breeder Consequences LWR
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facilities. These concerns are the
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Technological applicability Geologi
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It must be noted, that net risks an
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p Once-through fast reactor fuel. T
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Table E.1 Recycling Plant Functions
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Table E.3 Conventional Fuel Fabrica
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eactor. A summary of inputs from in
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