The FuTure oF nuclear Fuel cycle - MIT Energy Initiative

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Figure 6.10 total amount of tru in the System (base case) 16,000 MThM 12,000 8,000 oTc MoX Fr cr=0.75 Fr cr=1.00 Fr cr=1.23 4,000 0 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100 2110 Time (year) p In the breeder scheme: TRU producers (LWR) are replaced by TRU producers (Fast Breeders), which adds to the overall growth in TRU inventories, and end up with a higher total inventory than the once-through cycle. As seen in Fig 6.10, starting from a total TRU inventory of 840 tHM (600 tHM in interim storage, 125 tHM in cooling storage, and 115 tHM in LWR cores), the inventory reaches 11,785 tHM in the OTC scenario in the year 2100. However, adoption of the MOX scheme reduces the inventory by a small amount, while the fast burner reactors yield further reduction. The breeder on the other hand ends up increasing the TRU inventory in the entire system slightly above the OTC case. As can be seen in Figure 6.11 for the self-sufficient fast reactor case at the intermediate growth rate of 2.5%, once the TRU legacy is depleted, the TRU becomes mainly located in the cooling storage (at-reactor pools) and in the reactor cores themselves. To the extent the reactor cores may be considered more secure than interim storage, there is some advantage from a proliferation point of view. Additionally, little TRU is sent to the repository compared to the Once-Through option. However, if at some point in the future the nuclear energy system starts being abandoned in favor of an alternative energy source, the TRU inventory in the entire system will have to be dealt with. Some of it will be used as fuel in the reactors operating at that time. However, a disposal option will be needed at some point in the future, or pure burners will have to be deployed for many decades to reduce the TRU inventory. impaCt on repoSitory needS Although the recycling options dramatically reduce the total mass of wastes (95% w of the spent UO 2 fuel is recovered and recycled), they do not eliminate the necessity of a deep repository, as fission products and unrecoverable TRU amounts (losses) still have to be disposed of. Figure 6.12 shows the total mass of HLW destined to a repository in the various schemes for the base growth case. In the recycling schemes, the assumption of 1% unrecoverable heavy metals is made. Recall that the repository is assumed to open in 2028 and HLW is sent to disposal 25 years after it is generated. chapter 6: analysis of Fuel cycle options 87
Figure 6.11 location of the tru inventories (Base Case Growth of 2.5% Per Year and the Self-Sustaining Fast Reactor) 10,000 MThM 6,666 3,333 Tru in wastes Tru in interim storage and reprocessing plants Tru in cooling storages Tru in fuel fabrication plants Tru in Fr cores Tru in lWr cores 0 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100 2110 Time (year) Figure 6.12 total amount of hlW in repository to open in 2028 (base case) 8M 6M oTc MoX Fr cr=0.5 Fr cr=1.23 ThIM 4M 2M 0 2008 Time (year) 2018 2028 2038 2048 2058 2068 2078 2088 2098 2108 note: cr = 0.5 line lies on top of cr = 1.23 line As expected, the OTC generates the largest amount of HLW in terms of mass. The current spent fuel legacy (56,800 tHM) is transferred to the repository in 2028. The accumulation of spent UO 2 fuel in the repository reaches 444,000 tIHM in 2108. In addition, about two thirds as much as this amount will be waiting in interim storage: 293,000 tIHM in 2108. For comparison, the HLW in the repository rises to only 63,000 tIHM in 2108 in the TTC scenario, plus about two thirds of this amount in interim storage (43,000 tIHM). The HLW amounts in the repository are even smaller for the FR schemes. However, the mass is not an appropriate metric to compare the different scenarios (see Chapter 5: Waste Management). Wastes vary in decay heat, volume (including packages) and radio-toxicity. Figure 6.13 shows the aggregated amount of wastes using the densification factors given in Table 6.4 as a measure of repository size and cost. 88 MIT STudy on The FuTure oF nuclear Fuel cycle
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Other Reports in This Series The Fu
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MIT Nuclear Fuel Cycle Study Adviso
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vi MIT STudy on The FuTure oF nucle
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viii MIT STudy on The FuTure oF nuc
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Study Findings and Recommendations
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Recommendation We recommend that a
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p Innovative nuclear energy applica
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p In line with many of our R&D reco
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The “once through” or open fuel
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have been implemented slowly. This
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Recommendation We recommend that th
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oped policies for specific wastes r
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nuClear Fuel CyCleS The united Stat
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- The primary differences were in t
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Recommendation Integrated system st
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Table 1.2 Summary of R&D Recommenda
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18 MIT STudy on The FuTure oF nucle
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the once-through Fuel Cycle for lig
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tricity costs. Waste management cos
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Figure 2.3 partial recycle of lWr S
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history of the nuclear Fuel Cycle B
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• What is the impact of timing of
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nuclear fuel cycles, the wastes (SN
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Because ore demand is closely coupl
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eStimatinG Future CoStS oF uranium
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Page 59 and 60: CitationS and noteS 1. Uranium 2007
Page 61 and 62: If SNF is to be shipped, typically
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Page 75 and 76: Table 5.1 United States Waste Class
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Page 85 and 86: CitationS and noteS 1. A Handbook f
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Page 89 and 90: energy spectrum centered at higher
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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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154 MIT STudy on The FuTure oF nucl
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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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