Abstract
Nuclear energy is attracting revived interest as a potential alternate for electric power generation in the event of increased concerns about global warming. Compared to energy produced by combustion of a carbon atom in coal, fission of a U-235 atom will produce about 10 millions times more energy. However, storage of the nuclear waste is an environmental issue. This chapter has four sections with a major focus on introduction of nuclear power plants and reprocessing of spent nuclear fuels. Different nuclear fuel cycles and nuclear power reactors are introduced in the first section, and the cost–benefits of different energy sources are compared. Fuel burnup and formation of fission products are discussed along with operational impacts and risk analyses in the second section. The third section discusses design of nuclear structural components and various degradation modes. Section four discusses reprocessing issues of nuclear spent fuels. Reprocessing of spent nuclear fuel may be an economically viable option and reduces high-radioactive load in the nuclear waste repositories as well. However, there is a concern about proliferation of weapons-grade plutonium separated during reprocessing. Containment of radionuclides in different waste forms is also discussed in this section.
References
Anderson MT, Crawford SL, Cumblidge SE, Denslow KM, Diaz AA, Doctor SR (2007) NUREG/CR-6933, PNNL-16292, March 2007
Bloom EE (1998) J Nucl Mater 263:7
Bond AP, Dundar HJ (1977) In: Staehle RW, Hochmann J, MdRight RD, Slater RE (eds) Stress corrosion cracking of ferritic stainless steels. NACE, Houston, p 1136
Brinkman CR, Korth GE (1973) Heat-to-heat variations in the fatigue and creep–fatigue behavior of AISI type 304 stainless steel at 593°C. J Nucl Mater 48(3):293–306
Calonne V, Gourgues AF, Pineau A (2004) Fatigue Fract Eng Mater Struct 27:31–43
CANDU Reactors, Information from: http://www.aecl.ca/Reactors.htm
Capdevila C, Miller MK, Russell KF, Chao J, Gonzalez-Carrasco JL (2008) Phase separation in PM 2000 Fe-base ODS alloy. Mater Sci Eng A 490:277–288
Caravaca C, De Cordoba G, Tomas MJ, Rosado M (2007) Electrochemical behavior of Gd in molten LiCl-KCl. J Nucl Mater 360:25–31
Carmack WJ et al (2009) Metallic fuels for advanced reactors. J Nucl Mater 392(2):139–150
Carter ML (2004) Mater Res Bull 39:1075
Castrillejo Y, Bermejo MR, Pardo R, Martinez AM (2002) Use of electrochemical techniques for study of solubilization of cerium compounds in molten chloride. J Electroanal Chem 322:124–140
Castrillejo Y et al (2005a) Electrochemistry of Dy in LiCl-KCl. Electrochim Acta 50:2047–2057
Castrillejo Y et al (2005b) Electrochemical behavior of Pr(III) in molten chlorides. J Electroanal Chem 575:61–74
Castrillejo J et al (2005c) Electrochim Acta 50:2047; (2006) 51:1941; (2008) 53:5106; (2005) J Electroanal Chem 575:61–74
Celestian AJ et al (2008) J Am Chem Soc 130:11689
Charit I, Murty KL (2008) Creep behavior of niobium-modified zirconium alloys. J Nucl Mater 374(3):354–363
Chen GZ, Fray DJ, Farthing TW (2000) Nature 407(6802):361–364
Choo KN, Pyun SI, Kim YS (1995) J Nucl Mater 226:9–14
Chung HM, Leax TR (1990) Mater Sci Technol 6:249–262
Cicero G, Catellani A, Galli G (2004) Phys Rev Lett 93:016102
Cicero S, Setien J, Gorrochategui I (2009) Nucl Eng Des 239:16–22
Cohen U (1983) J Electrochem Soc 130:1480
Cookson JM, Was GS (1995) Proceedings of the seventh international conference on environmental degradation of materials in nuclear power systems water reactors, NACE, Breckenridge, p 1109
Dahlkamp F (1993) Uranium ore deposits. Springer, Berlin. ISBN 3540532641
Domagala RF, McPherson DJ (1954) Trans AIME 200:238
“Economics of Nuclear Power” reported in http://www.world-nuclear.org/info/inf02.html
Fullwood RR, Hall RE (1988) Probabilistic risk assessment in the nuclear power industry: fundamentals and applications. Pergamon Press, Oxford
Galkin NP, Veryatin UD, Yakhonin IF, Lugonov AF, Dymkov YM (1982) The conversion of uranium hexafluoride to dioxide. At Energ 52(1):36–39
Gaune-Escard M, Bogacz A, Rycerz L, Szczepaniak W (1994) Thermochim Acta 236:67–80
Gogotsi YG et al (1996) J Mater Chem 6:595–604
Gong W, Gaune-Escard M, Rycerz L (2005) J Alloys Compd 396:92–99
Grobe M, Lehmann E, Steinbruck M, Kuhne G, Stuckert J (2009) J Nucl Mater 385:339–345
Grossbeck ML, Ehrlich K, Wassilew C (1990) An assessment of tensile, irradiation creep, creep rupture, and fatigue behavior in austenitic stainless steels with emphasis on spectral effects. J Nucl Mater 174(2–3):264–281
Guo H, Wang D, Gong S, Xu H (2014) Effect of reactive elements on oxidation behavior of β-NiAl at 1200 °C. Corros Sci 78:369–377
Hallstadius L, Johnson S, Lahoda E (2012) Prog Nucl Energy 57:71–76
Hamel C, Chamelot P, Taxil P (2004) Nd cathode process in molten fluoride. Electrochim Acta 49:4467–4476
Hazebroucq S, Picard GS, Adamo C (2005) A theoretical investigation of Gd(III) salvation in molten salts. J Chem Phys 122:224512
He C, Wu X, Shen J, Chu PK (2012) Nano Lett 12:1545–1548
Hejzlar P, Mattingly BT, Todreas NE, Driscoll MJ (1997) Nucl Eng Des 167:375–392
Henager CH et al (2008) J Nucl Mater 378:9–16
Heuer AH, Hovis DB, Smialek JL, Gleeson B (2011) Alumina scale formation: a new perspective. J Am Ceram Soc 94:S146–S153
Hirayama H, Kawakubo T, Goto A (1989) J Am Ceram Soc 72:2049–2053
Holt RA (1974) J Nucl Mater 51: 309; (1974) 50: 207
IAEA (2001) Safety assessment and verification for nuclear power plants – a safety guide. Safety standards series, No. NS-G-1.2. ISBN 92-0-101601-8
Ikeda M, Miyagi Y, Igarashi K, Mochinaga J, Ohno H (1988) The 20th symposium on molten salt chemistry, C303, Yokohama, 10 Nov 1988
Jayet-Gendrot S, Ould P, Meylogan T (1998) Nucl Eng Des 184:3–11
Jeong I-S, Ha G-H, Jun H-I (2009) J Loss Prev Process Ind 22:879–883
Jeong IS, Kim W, Kim TR, Jeon HI (2011) Nucl Eng Tech 43:83–88
Jevremovic T (2005) Nuclear principles in engineering. Springer, New York
Jiang C et al (2009) Phys Rev B 79:132110
Kawaguchi S, Sakamoto N, Takano G, Matsuda F, Kikuchi Y, Mraz L (1997) Nucl Eng Des 174:273–285
Kerr R, Solana F, Bernstein IM, Thompson AW (1987) Metall Trans A 18A:1011
Kim WJ, Hwang HS, Park JY, Ryu WS (2003) J Mater Lett 22:581–584
Kimura A et al (1996) Irradiation hardening of reduced activation martensitic steels. J Nucl Mater 233–237(Pt A):319–325
Kiran Kumar M, Aggarwal S, Kain V, Saario T, Bojinov M (2010) Nucl Eng Des 240:985–994
Klueh RL, Alexander DJ (1996) Impact behavior of reduced-activation steels irradiated to 24 dpa. J Nucl Mater 233–237(Pt A):336–341
Klueh RL, Shingledecker JP, Swinderman RW, Hoelzer DT (2005) Oxide dispersion-strengthened steels: a comparison of some commercial and experimental alloys. J Nucl Mater 341:103–114
Knief RA (1992) Nuclear engineering: theory and technology of commercial nuclear power. Hemisphere Publishing Corporation, Washington DC
Koyama T, Iizuka M, Shoji Y, Fujita R, Tanaka H, Kobayashi T, Tokiwai M (1997) An experimental study of molten salt reprocessing. J Nucl Sci Tech 34(4):384–393
Koyama T, Hijikata T, Usami T, Inoue T, Kitawaki S, Shinozaki T, Myochin M (2007) Integrated experiments on electrometallurgical processing using PuO2. J Nucl Sci Tech 44(3):382–392
Kraft T, Nickel KG, Gogotsi YG (1998) J Mater Sci 33:4357–4364
Krass AS, Boskma P, Elzen B, Smit WA (1983) Uranium enrichment and nuclear weapon proliferation. Taylor and Francis, London
Kuan P, Hanson DJ (1991) INL report EGG-M-91375
Kuznetsov SA, Hayashi H, Minato K, Gauno-Escard M (2005) Determination of U and RE metals separation coefficients in LiCl-KCl melt. J Nucl Mater 344:169–172
Kwon J, Woo S, Lee Y, Park J, Park Y (2001) Nucl Eng Des 206:35–44
Leslie WC (1977) Stress corrosion cracking and hydrogen embrittlement of iron base alloys. NACE, Houston, p 52
Li J, Yang Y, Li L, Lou J, Luo X, Huang B (2013) J Appl Phys 113:023516
Lide DR (1997) Handbook of chemistry and physics, 78th edn. CRC Press, Boca Raton
Lim J, Hwang IS, Kim JH (2013) Design of alumina forming FeCrAl steels for lead cooled fast reactors. J Nucl Mater 441:650–660
Lippmann W, Knorr J, Nöring R, Umbreit M (2001) Nucl Eng Des 205:13–22
Liu Y, Su KH, Wang X, Wang Y, Zeng QF, Cheng LF, Zhang LT (2010) Chem Phys Lett 501:87–92
Liu Y, Su KH, Zeng QF, Cheng LF, Zhang LT (2012) Theor Chem Acc 131:1101
Makhijani A, Chalmers L, Smith B. Uranium Enrichment, Institute for Energy and Environmental Research, 15 Oct 2004. http://www.ieer.org/reports/uranium/enrichment.pdf
Maziasz PJ (1993) Overview of microstructural evolution in neutron-irradiated austenitic stainless steels. J Nucl Mater 205:118–145
Maziasz PJ, McHargue CJ (1987) Int Metal Rev 32:190
MIN KS, Nam SW (2003) Correlation between characteristics of grain boundary carbides and creep-fatigue properties in AISI 321 stainless steel. J Nucl Mater 322:91–97
Morss LR, Edelstein NM, Fuger J (eds) (2006) The chemistry of the actinide and transactinide elements, 3rd edn. Springer, Dordrecht
Murray RL (2001) Nuclear energy: an introduction to the concepts, systems, and applications of nuclear processes. Butterworth Heinemann, Woburn
Nam SW (2002) Assessment of damage and life prediction of austenitic stainless steel under high temperature creep-fatigue interaction condition. Mater Sci Eng A322(1–2):64–72
Nelson AT, Sooby ES, Kim YJ, Cheng B, Maloy SA (2013) High temperature oxidation of molybdenum in water vapor environments. J Nucl Mater 448(1–3):441–447
Ni N, Lozano-Perez S, Sykes J, Grovenor C (2011) Ultramicroscopy 111:123–130
Nilsson JO (1988), ASTM STP 942, 543, American Society for Testing Materials, Philadelphia
OCDE/NEA report: accelerator-driven systems (ADS) and fast reactors (FR) in advanced nuclear fuel cycles. A comparative study, (2002) 1
Okamoto Y (1998) Phys Rev B 58:6760
Olander DR (1978) The Gas Centrifuge. Scientific American, August 1978, p 37
Opila EJ (2003) J Am Ceram Soc 86:1238–1248
Opila EJ, Hann RE Jr (1997) J Am Ceram Soc 80:197–205
Pint BA, Terrani KA, Brady MP, Cheng T, Keiser JR (2013) High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments. J Nucl Mater 440:420–427
RHO BS, Nam SW (2002) Heat effects of nitrogen on low-cycle fatigue properties of Type 304L austenitic stainless steels tested with and without tensile strain hold. J Nucl Mater 300:65–72
Roy JJ et al (1996) J Electrochem Soc 143:2487
Rudling P, Adamson R, Cox B, Garzarolli F, Strasser A (2008) High burn-up fuel issues. Nucl Eng Technol 40(1):1–8
Sakamura Y et al (1998) J Alloys Compd 271–273:592–596
Senor DJ, Youngblood GE, Moore CE, Trimble DJ, Newsome GA, Woods JJ (1996) Fusion Technol 30:943
Serrano K, Taxil P (1999) J Appl Electrochem 29:505
Shack WJ, Kassner TF (1994) Review of Environmental Effects on Fatigue Crack Growth of Austenitic Stainless Steels, NUREG/CR-6176, ANL-94/1, U.S. Nuclear Regulatory Commission, Washington, DC, NRC FIN L2424
Shapiro J (1990) Radiation protection, 3rd edn. Harvard University Press, Cambridge, MA
Shen X, Pantelides ST (2013) J Phys Chem Lett 4:100–104
Shiba K et al (1996) Irradiation response on mechanical properties of neutron irradiated F82H. J Nucl Mater 233–237(Pt A):309–312
Shimada S, Onuma T, Kiyono H (2006) J Am Ceram Soc 89:1218–1225
Shirai O, Iizuka M, Iwai T, Suzuki Y, Arai Y (2000) J Electroanal Chem 490:31–36
Shoesmith DW (2006) Corrosion 62:703–722
Storm van Leeuwen JW, Smith P (2005) Nuclear power: the energy balance. http://www.stormsmith.nl/
Suauzay M et al (2004) Creep-fatigue behaviour of an AISI stainless steel at 550°C. Nucl Eng Des 232:219–236
Suzuki S, Saito K, Kodama M, Shima S, Saito T (1991) SmiRt 11 transactions, vol. D, August 1991, Tokyo
Takagi R, Rycerz L, Gaune-Escard M (1997) J Alloys Compd 257:134–136
Tan L, Allen TR, Barringer E (2009) J Nucl Mater 394:95–101
Terrani KA, Zinkle SL, Snead LL (2013) Advanced oxidation-resistant iron-based alloys for LWR fuel cladding. J Nuc Mater 448:374–379
Thorium fuel cycle–potential benefits and challenges, International Atomic Energy Agency, Vienna, IAEA-TECDOC-1450, May 2005
Tsuji H, Nakajima H (1994) Creep-fatigue Damage Evaluation of a Nickel-base Heat-resistant Alloy Hastelloy XR in Simulated HTGR Helium Gas Environment. J Nucl Mater 208:293–299
Van Der Schaaf B (1988) The effect of neutron irradiation on the fatigue and fatigue-creep behaviour of structural materials. J Nucl Mater 155–157:156–163
Wang ZX, Xue F, Guo WH, Shi HJ, Zhang GD, Shu G (2010) Nucl Eng Des 240:2538–2543
Wigeland RA et al (2006) Nucl Technol 154:95
Wray P, Marra J (2011) Materials for nuclear energy in the post-Fukushima era. Am Ceram Soc Bull 90(6):24–28
Yang YS, Kang YH, Lee HK (1997) Estimation of optimum experimental parameters in chlorination of UO2 with Cl2 gas and carbon for UCl4. Mater Chem Phys 50:243–247
Yilmazbahyan A, Breval E, Motta AT, Comstock RJ (2006) J Nucl Mater 349:265–281
Yokobori T, Yokobori AT Jr (2001) High temperature creep, fatigue and creep-fatigue Interaction in engineering materials. Int J Press Vessel Pip 78:903–908
Zhang H et al (2010) J Am Ceram Soc 93:1148–1155
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Raja, K.S., Pesic, B., Misra, M. (2015). Nuclear Energy and Environmental Impact. In: Chen, WY., Suzuki, T., Lackner, M. (eds) Handbook of Climate Change Mitigation and Adaptation. Springer, New York, NY. https://doi.org/10.1007/978-1-4614-6431-0_30-2
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