PLENTIFUL ENERGY

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ACRONYMS AEC AECL ANL ANL-E ANL-W ANS APDA ASPO ATWS BR BWR CANDU CBI CEFR CEO CDFR CFR CGE CIAE CNNC CP CPFR CRBR CRIEPI DFR DOE EBWR EEDB EFL EPA FARET FBTR FCF FFTF FMF GE GEM GNEC GW Atomic Energy Commission Atomic Energy of Canada Limited Argonne National Laboratory Argonne National Laboratory-East Argonne National Laboratory-West American Nuclear Society Atomic Power Development Associates Association for the Study of Peak Oil and Gas Anticipated transient without scram Breeding ratio Boiling water reactor Canada Deuterium-Uranium Reactor Chicago Bridge & Iron Company China Experimental Fast Reactor Chief executive officer Commercial Demonstration Fast Reactor Code of federal regulation Canadian General Electric China Institute of Atomic Energy China National Nuclear Corporation Chicago Pile China Prototype Fast Reactor Clinch River Breeder Reactor Central Research Institute of Electric Power Industry Dounreay Fast Reactor Department of Energy Experimental Boiling Water reactor Energy economics data base Experimental Fuel Laboratory Environmental Protection Agency Fast Reactor Test Facility Fat Breeder Test Reactor Fuel Cycle Facility or Fuel Conditioning Facility High Flux Test Facility Fuel Manufacturing Facility General Electric Gas expansion module General Nuclear Engineering Company Giga watt 389
HCDA HFEF HM HWR HTR IAEA ICRP IEA IFR IHX INFCE INL JAEA JAPC JSFR KAERI LAMPRE LANL LMFBR LNG LSPB LWR MIT MOX MW MWD/T NAC NAS NASAP NPD NRC NRTS NWPA OCS PFBR PFR PNC PRISM PUREX QA QC R&D RBCB RDT Hypothetical core disruptive accident Hot Fuel Examination Facility Heavy metal Heavy water reactor High Temperature Gas-cooled Reactor International Atomic Energy Agency International Commission on Radiological Protection International Energy Agency Integral Fast Reactor Intermediate heat exchanger International Nuclear Fuel Cycle Evaluation Idaho National Laboratory Japan Atomic Energy Agency Japan Atomic Power Company JAEA Sodium-cooled Fast Reactor Korea Atomic Energy Research Institute Los Alamos Molten Plutonium Reactor Experiment Los Alamos National Laboratory Liquid metal fast breeder reactor Liquefied natural gas Large Scale Prototype Breeder Light water reactor Massachusetts Institute of Technology Mixed oxide Megawatt Megawatt-days per tone Nuclear Assurance Corporation National Academy of Sciences Nonproliferation Alternative Systems Assessment program Nuclear Power Demonstration Nuclear Regulatory Commission National Reactor Testing Station National Waste Policy Act Operator control station Prototype Fast Breeder Reactor Prototype Fast Reactor Power Reactor and Nuclear Fuel Cycle Development Corporation Power Reactor Innovative Small Module Plutonium Uranium Extraction Quality assurance Quality control Research and development Run beyond cladding breach Reactor Development and Technology, a Division of AEC 390
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PLENTIFUL ENERGY The Story of the I
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Copyright © 2011 Charles E. Till a
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CONTENTS FOREWORD .................
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CHAPTER 10 APPLICATION OF PYROPROCE
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FOREWORD On a breezy December day i
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CHAPTER 1 ARGONNE NATIONAL LABORATO
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even now is straining the limits of
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with events and time. Till saw the
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it, I saw how a national laboratory
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Figure 1-2. West stands of the Stag
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development of nuclear power for ci
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depended on U.S. ability to maintai
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construction funding kept increasin
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faced a nightmarish combination of
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concept in the next decade.) In sti
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was based on EBR-I experience, but
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Figure 1-9. Experimental Breeder Re
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Figure 1-11. Rendering of the EBR-I
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performance. But the decision had b
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its shakedown in early years it jus
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sense primarily a commercial power
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without electrical generation, the
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Its purpose was to demonstrate the
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of each period, which the managemen
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CHAPTER 2 THE INTEGRAL FAST REACTOR
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A line had been pursued that the re
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The IFR refining process also produ
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director of Argonne a year or two b
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eporting on nuclear power developme
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A few weeks later, the mid-term ele
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2.6 Summary In late 1983, the line
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Argonne would be. My Ph.D. at Imper
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I had worked at the United Kingdom
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hadn‘t bothered us with it. But t
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But I had gone over and over the on
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laboratories.‖ Incidentally, late
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Argonne by this time was one of sev
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3.1.2 Life at the Laboratory in the
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An anecdote: In the cooperative arr
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Cycle Facility‖ went. We pushed i
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(LMFBR), which assumed a very rapid
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the pool was a settled issue; it wa
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During the early stage of the IFR p
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scientific work, not on non-essenti
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e generally held, even as facts inc
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cf per day from Canada via pipeline
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serious, and it is made more seriou
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global economy. The LWR, and the Ad
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supply 11%, and one, the world‘s
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Fatih Birol, has recently been quot
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gas production of little use in the
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expenditures during a decade starti
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thousand tonnes in one large increm
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But the principal line of developme
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Tar sands and oil shale recovery ar
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14. W. H. Ziegler, C. J. Campbell,
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Argonne had been a part of the deve
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Breaches or holes in the fuel cladd
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waste. For efficiency in uranium us
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Further, as a metal, sodium does no
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to the boundaries and many leak fro
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is debatable, it remains our belief
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CHAPTER 6 IFR FUEL CHARACTERISTICS,
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To do this, an extraordinarily simp
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Further cementing the decision was
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the AEC, but the reactor operation
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hands-on access needed to accomplis
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temperature. However, a very substa
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It turned out that the high-plutoni
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In the column ―Pu content % heavy
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40 start-ups and shutdowns 5 15% ov
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During casting, a partial vacuum (1
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is in fact a new fuel. Plutonium-ba
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8. G. L. Hofman and L. C. Walters,
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characteristics necessary for this.
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exchangers, and the steam generator
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experiments, as mentioned; this has
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sufficient to allow radioactive rel
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In the IFR, this loss of the coolin
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Figure7- 2. Reactor outlet temperat
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for thermal expansion of heavy stru
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power to shut down power is basical
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criticality. The debris is in the f
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7.10.2 The EBR-I Partial Meltdown T
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7.11 Licensing Implications What ar
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The sodium flowing into the steam g
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[15] Provisions are also made to co
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disassembly comes, it is with a rea
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CHAPTER 8 THE PYROPROCESS In the ne
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EBR-II purposes, and it established
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valuable fuel constituents, uranium
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and materials and it had been renam
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The first operation is done in the
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into the receiver crucible. The hea
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In the final step, the pins are arr
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Spent Fuel Processed, kg effective
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products, highly radioactive and se
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its own bayonet-style partial inter
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If the bond sodium along with the s
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CHAPTER 9 THE BASIS OF THE ELECTROR
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Whether or not a given reaction can
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9.3 Kinetics of the Reactions Chemi
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The exponential exp((E f -E b )/RT)
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The electrorefining process brings
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cathode operation. Once the solutio
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Table 9-2. Measured data and calcul
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All four measurements show that eve
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The free energy of the reaction of
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2. At an actinide chloride ratio of
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CHAPTER 10 APPLICATION OF PYROPROCE
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10.2 Electrolytic Reduction Step 10
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The pyrochemical process simply sup
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Figure 10-1. Electrolytic reduction
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The distribution of fuel constituen
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an electrorefiner with a 5001,000 k
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aqueous reprocessing plant. The eco
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Li metal at the cathode. Lithium me
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4. D. W. Dees and J. P. Ackerman,
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Our intent for the IFR technology w
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dose to any member of the public mu
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IFR process, as we shall see, does
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Relative Radiological Toxicity uran
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doses from Tc-99 and I-129 equilibr
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Fraction of Initial Actinide, % pro
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long-lived fission products and tra
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to decay to the point where they co
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References 1. ―Nuclear Waste Poli
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12.1 Introduction Assessment of a p
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History provides empirical evidence
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program offered nations help with n
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Other nations are recycling their s
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uranium-233 cycle has been half-hea
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electrorefiner salt. And this, of c
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those concentrations in making the
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chance of ―pre-ignition‖ leadin
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It is now known that the plutonium
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12.8 Monitoring of Processes Always
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[18] In it he shows that with a spo
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Such a system tracks the quantity a
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weapons grade plutonium. Levels of
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12.13 Summary In IFR technology the
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12. T. P. McLaughlin, et al., ―A
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The earliest fast reactors designed
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India, too, has successfully operat
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levels, actually higher than the di
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for the backend of the fuel cycle,
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$/lb Uranium Price, $/lb U3O8 the f
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the once-through fuel cycle. Howeve
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$/kg 1200 1000 $1000/kg Rep Cost Pu
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Table 13-7. Summary Comparison of F
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fabrication. This, along with a low
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Fissile Cost, $/gm-fissile Fuel Cyc
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13.6 System Aspects The previous se
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waste streams have no long-term dec
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5. S. C. Chetal, ―India‘s Fast
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capacity over this century, in a sy
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thermal properties of NaK—the boi
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It is suspected that the lead corro
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Neutron Yield, Eta Value A = number
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to maintain a hard spectrum, the fu
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Table 14-3. Effects of fuel pin dia
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Fuel Volume Fraction have a large e
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neutron leakages from the core are
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like breeding, does increase such d
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substantial advantage to start with
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Doubling Time, yrs the reactivity c
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14.7 Worldwide Fast Reactor Experie
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limit to its life. The ingenuity of
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Nuclear Capacity, GWe the replaceme
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14.9 How to Deploy Pyroprocessing P
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construction projects. They may see
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inferior to sodium in their thermal
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5. Federation of American Scientist
Page 349 and 350: Supporting the reactor design and c
Page 352 and 353: ACKNOWLEDGEMENTS In beginning this
Page 354 and 355: APPENDIX A DETAILED EXPLANATION OF
Page 356 and 357: The actinide metals (uranium, pluto
Page 358 and 359: As noted above, the interactions ri
Page 360 and 361: 3. Equilibrium coefficients give th
Page 362 and 363: ion is created at the anode. Bulk t
Page 364 and 365: proceed spontaneously. If the magni
Page 366 and 367: product chlorides are highly stable
Page 368 and 369: increases with increasing temperatu
Page 370 and 371: Equilibrium in a chemical system is
Page 372 and 373: Exp(-ΔG o /RT) = [ U / Pu ] [ U /
Page 374 and 375: ―in solution.‖ More Pu added to
Page 376 and 377: appropriate values are used for the
Page 378 and 379: A.9.5 The Second Cathode Regime: On
Page 380 and 381: in the real world. Uranium dendrite
Page 382 and 383: This is the significant number. The
Page 384 and 385: For those who are curious, the elec
Page 386 and 387: of concentration of uranium chlorid
Page 388 and 389: agreement with the measured ratio w
Page 390 and 391: eference 7. The important calculati
Page 392 and 393: as well. The numbers were obtained
Page 394 and 395: Run3: Plutonium isn’t, Uranium is
Page 396 and 397: The final actinide chloride ratios
Page 398: values of several of the constants
Page 404: ABOUT THE AUTHORS Dr. CHARLES E. TI
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