Minor actinide: Difference between revisions
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The '''minor actinides''' are the [[actinide]] elements in used [[nuclear fuel]] other than [[uranium]] and [[plutonium]], which are termed the [[major actinide]]s. The minor actinides include [[neptunium]] (element 93), [[americium]] (element 95), [[curium]] (element 96), [[berkelium]] (element 97), [[californium]] (element 98), [[einsteinium]] (element 99), and [[fermium]] (element 100).<ref>{{cite book|last=Moyer|first=Bruce A.|title=Ion Exchange and Solvent Extraction: A Series of Advances, Volume 19|year=2009|publisher=CRC Press|isbn=9781420059700|pages=120|url=https://books.google.com/books?id=NTgjUaLZiDsC&pg=PA120#v=onepage&q&f=false}}</ref> The most important isotopes in [[spent nuclear fuel]] are [[neptunium-237]], [[americium-241]], [[americium-243]], [[curium]]-242 through -248, and [[californium]]-249 through -252. |
The '''minor actinides''' are the [[actinide]] elements in used [[nuclear fuel]] other than [[uranium]] and [[plutonium]], which are termed the [[major actinide]]s. The minor actinides include [[neptunium]] (element 93), [[americium]] (element 95), [[curium]] (element 96), [[berkelium]] (element 97), [[californium]] (element 98), [[einsteinium]] (element 99), and [[fermium]] (element 100).<ref>{{cite book|last=Moyer|first=Bruce A.|title=Ion Exchange and Solvent Extraction: A Series of Advances, Volume 19|year=2009|publisher=CRC Press|isbn=9781420059700|pages=120|url=https://books.google.com/books?id=NTgjUaLZiDsC&pg=PA120#v=onepage&q&f=false}}</ref> The most important isotopes of these elements in [[spent nuclear fuel]] are [[neptunium-237]], [[americium-241]], [[americium-243]], [[curium]]-242 through -248, and [[californium]]-249 through -252. |
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Plutonium and the minor [[actinide]]s will be responsible for the bulk of the [[radiotoxicity]] and heat generation of [[used nuclear fuel]] in the medium term (300 to 20,000 years in the [[future]]).<ref>{{cite book|last=Stacey|first=Weston M.|title=Nuclear Reactor Physics|year=2007|publisher=John Wiley & Sons|isbn=9783527406791|pages=240|url=https://books.google.com/books?id=y1UgcgVSXSkC&pg=PA240#v=onepage&q&f=false}}</ref> |
Plutonium and the minor [[actinide]]s will be responsible for the bulk of the [[radiotoxicity]] and heat generation of [[used nuclear fuel]] in the medium term (300 to 20,000 years in the [[future]]).<ref>{{cite book|last=Stacey|first=Weston M.|title=Nuclear Reactor Physics|year=2007|publisher=John Wiley & Sons|isbn=9783527406791|pages=240|url=https://books.google.com/books?id=y1UgcgVSXSkC&pg=PA240#v=onepage&q&f=false}}</ref> |
Revision as of 17:54, 20 December 2019
This article needs additional citations for verification. (April 2009) |
The minor actinides are the actinide elements in used nuclear fuel other than uranium and plutonium, which are termed the major actinides. The minor actinides include neptunium (element 93), americium (element 95), curium (element 96), berkelium (element 97), californium (element 98), einsteinium (element 99), and fermium (element 100).[2] The most important isotopes of these elements in spent nuclear fuel are neptunium-237, americium-241, americium-243, curium-242 through -248, and californium-249 through -252.
Plutonium and the minor actinides will be responsible for the bulk of the radiotoxicity and heat generation of used nuclear fuel in the medium term (300 to 20,000 years in the future).[3]
The plutonium from a power reactor tends to have a greater amount of plutonium-241 than the plutonium generated by the lower burnup operations designed to create weapons-grade plutonium. Because the reactor-grade plutonium contains so much 241Pu, the presence of americium-241 makes the plutonium less suitable for making a nuclear weapon. The ingrowth of americium in plutonium is one of the methods for identifying the origin of an unknown sample of plutonium and the time since it was last separated chemically from the americium.
Americium is commonly used in industry as both an alpha particle and as a low photon energy gamma radiation source. For instance it is used in many smoke detectors. Americium can be formed by neutron capture of 239Pu and 240Pu, forming 241Pu which then beta decays to 241Am.[4] In general, as the energy of the neutrons increases, the ratio of the fission cross section to the neutron capture cross section changes in favour of fission. Hence, if MOX is used in a thermal reactor such as a boiling water reactor (BWR) or pressurized water reactor (PWR) then more americium can be expected in the used fuel than that from a fast neutron reactor.[5]
Some of the minor actinides have been found in fallout from bomb tests. See Actinides in the environment for details.
Isotope | Fraction | DLWR | Dfast | Dsuperthermal |
---|---|---|---|---|
237 Np |
0.0539 | 1.12 | -0.59 | -0.46 |
238 Pu |
0.0364 | 0.17 | -1.36 | -0.13 |
239 Pu |
0.451 | -0.67 | -1.46 | -1.07 |
240 Pu |
0.206 | 0.44 | -0.96 | 0.14 |
241 Pu |
0.121 | -0.56 | -1.24 | -0.86 |
242 Pu |
0.0813 | 1.76 | -0.44 | 1.12 |
241 Am |
0.0242 | 1.12 | -0.62 | -0.54 |
242m Am |
0.000088 | 0.15 | -1.36 | -1.53 |
243 Am |
0.0179 | 0.82 | -0.60 | 0.21 |
243 Cm |
0.00011 | -1.90 | -2.13 | -1.63 |
244 Cm |
0.00765 | -0.15 | -1.39 | -0.48 |
245 Cm |
0.000638 | -1.48 | -2.51 | -1.37 |
Weighted sum | -0.03 | -1.16 | -0.51 |
References
- ^ Sasahara, Akihiro; Matsumura, Tetsuo; Nicolaou, Giorgos; Papaioannou, Dimitri (April 2004). "Neutron and Gamma Ray Source Evaluation of LWR High Burn-up UO2 and MOX Spent Fuels". Journal of Nuclear Science and Technology. 41 (4): 448–456. doi:10.3327/jnst.41.448. Archived from the original on 2010-11-19.
- ^ Moyer, Bruce A. (2009). Ion Exchange and Solvent Extraction: A Series of Advances, Volume 19. CRC Press. p. 120. ISBN 9781420059700.
- ^ Stacey, Weston M. (2007). Nuclear Reactor Physics. John Wiley & Sons. p. 240. ISBN 9783527406791.
- ^ Raj, Gurdeep (2008). Advanced Inorganic Chemistry Vol-1, 31st ed. Krishna Prakashan Media. p. 356. ISBN 9788187224037.
- ^ Berthou, V.; et al. (2003). "Transmutation characteristics in thermal and fast neutron spectra: application to americium" (PDF). Journal of Nuclear Materials. 320: 156–162. Bibcode:2003JNuM..320..156B. doi:10.1016/S0022-3115(03)00183-1.
- ^ Etienne Parent (2003). "Nuclear Fuel Cycles for Mid-Century Deployment" (PDF). MIT. p. 104. Archived from the original (PDF) on 2009-02-25.