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4-4 Table 4.0-1 gives some of the pertinent neutronic properties of the different fissile nuclides for a specific thermal-neutron energy. In discussing these properties,* it is necessary to distinguish between the two functions of a fissile material: the production of energy (i.e., power) and the production of ezcess neutrons which when absorbed by fertile material will produce additional fissile fuel. Nuclide Table 4.0-1. Nuclear Parameters of the Principal Fissile Nuclides 233U, 235U, 239Pu, and 241P~a9b at Thermal Energy (Neutron Energy = 0.0252 eV, velocity = 2200 m/sec) Cross Section (barns) ‘a uf uc a V n 23311 578 2 2 531 2 2 47 1 0.089 2 0.002 2.487 2 0.007 2.284 2 0.006 2351) 678 2 2 580 2 2 98 2 1 0.169 2 0.002 2.423 2 0.007 2.072 2 0.006 239Pu 1013 2 4 742 2 3 271 3 0.366 2 0.004 2.880 5 0.009 2.109 2 0.007 241Pu 1375 2 9 1007 7 368 2 8 0.365 2 0.009 2.934 2 0.012 2.149 2 0.014 ~~ a G. C. Hanna et al., Atomic Energ. Rev. 7, 3-92 (1969); figures in the referenced article were all given to one additional significant figure, b~a = uf + uc; a = uc/uf; v = neutrons produced per fission; 11 = neutrons produced per atom destroyed = v/(l + a). The energy-production efficiency of a fissile material is directly related to its neutron capture-to-fission ratio (a), the smaller the ratio the greater the fraction of neutron-nuclide interactions that are energy-producing fissions. As indicated by Table 4.0-1, at thermal energy the value of a is significantly smaller for 233U than for the other isotopes, and thus 233U has a greater energy-production efficiency than the other isotopes. (lhe energy released per fission differs only slightly for the above isotopes.) The neutron-production efficiency of a fissile material is determined by the number of neutrons produced per atom of fissile material destroyed (n), the higher the number the more the neutrons that will be available for absorption in fertile material. Table 4.0-1 shows that the n value for 233U is higher than that for any of the other nuclides, although plutonium would at first appear to be superior since it produces more neutrons per fission (v). The superiority of 233U results from the fact that a is lower for 233U and 0 = v/(l + a). Thus at thermal energies 233U both yields more energy and produces more neutrons per atom destroyed than any of the other fissile nuclides. In the energy range of interest for fast reactors (~0.05 - 4.0 MeV), the situation is not quite so straightforward. Here again, the a value for 233U is significantly lower than the values for the other fissile nuclides, and, moreover, the microscopic cross section for fission is higher (see Fig. 4.0-1). The energy release per fission of 233U is somewhat less than that of the plutonium nuclides, but the energy release per atom of 233U destroyed is significantly higher than for th, othcr nuclides. Thus, from ths standpoint *Much of this discussion on the neutronic properties of nuclides is based on refs. 1 - 3.
Y m I I I . aro ID0 10.00 4-5 ORNL-DWG 76-17705 ORNL-DWG76-47704 I J 0.04 aro +Do E(MeV) 3.0 2.8 , 2.6 9 2.4 2.2 2.0 1.8 I .6 0 ORNL-DWG 78-13 I- I I I 0. I 1.0 - E(MeV) ORNL-DNG 7647702 0 2 4 6 10 E(MeV) Fig. 4.0-1. Nuclear Parameters of the Principal Fissile and Fertile Nuclides at High Neutron Energies. a = ac/uf; rl = v/(l + a).
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Interim Assessment of the Denatured
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i L i b I, i L L bi L L Contract No
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1, L L t i Ltr 1 L L V PREFACE AND
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I L bi i; L 7.3.1. Possible Procedu
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i xi I b L ABSTRACT A fuel cycle th
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I b .- i, hd t t CHAPTER 1 INTRODUC
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Table 4.6-1. Comparison of Fuel Uti
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4-57 _I 10 10' 2 2' CASE NUMBER -.
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4-59 Most of the information availa
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4-63 on only the preliminary data p
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c e E c
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! 5-4 5.1. REACTOR RESEARCH AND DEV
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5-6 As has been pointed out above,
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5-8 the LMFBR on its reference cycl
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5-10 The fuel performance program u
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. 5.1.2. Government Research and De
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5-1 4 The first aspect of large pla
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5-1 6 and should also address metho
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I DATA BASE DEMu)pMENT DEMO DESIGN
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j ~ 5-20 The R,D&D costs are highes
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5-22 In the case of metal-clad oxid
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5-24 5.2.2. Research, Development,
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5-26 program, including hot testing
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c c
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6-4 persed areas ensured - a fact w
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6-6 6.1.2. Reactor Options The reac
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Reactor/Cycl ea LWR-U5(LE)/U-S LUR-
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6-10 6.1.3. Nuclear Policy Options,
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Table 6.1-4. Nuclear Policy Options
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SWU SWU 6-14 UZJS USILEINS WYI U5IL
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6-16 n nM MEDL nows.1 Option 4: In
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6-18 HM HEDL7OOl.70.3 Option 6: In
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SRCIFIED CONSTRUCTION LlMllLD INTRO
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50- 40 6-22 c Y \ VL - :-: F 30- -
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6-24 The potential nuclear contribu
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%- f $400 J 2 s 2, 1 THE LWR FOLLOW
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141.6 ST - U308 4 7.2 lo3 swu ENRIC
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6-30 reactor. Since this increase i
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‘9. ,1 ST ‘3O8 6-32 12 Kg HM I
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6-34 1HE LWR WITH FISSILE UUNIUM PC
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THE LWR WITH PURONIUM MlNUllUTlON A
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6-38 be located in energy centers a
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6-40 installed capacity must be han
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lm, 1 I I I I mf RR WITH UGHT rwrmi
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6-44 6.2.7. Converter-Breeder Syste
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25.2 ST swu 6-46 19 Kg fir Pu 13 Kg
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6-48 Table 6.3-2. Summary of Result
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6-50 (4) If all plutonium produced
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L 1 L u without benefit of U.S. exp
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7-9 Viewed solely from the plutoniu
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L L i; i; 7-1 1 routinely in LWRs a
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'I 7-1 3 t I: k: The isotopic compo
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U L L L L ld 1 i" * required 233U m
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7-25 7.3.2. Considerations in Comme
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7-29 7.4. ADEQUACY OF NUCLEAR POWER
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x ibd 1 .. I i, L -- i t Table 7.4-
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7-35 cycled in Pu/Th converters, th
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e Other e e e On the e 7-49 technol
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t a APPENDICES
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A-3 Appendix A. ISOTOPE SEPARATION
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I] 1- $i ill 8 LI b' The Gas Centri
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id A- 7 The Component Preparation L
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p; ‘U i-- L ,c c Japan A-1 1 Tabl
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13 A-13 L" efficient of the units d
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L L L t I h h u L; _- t f is throug
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u A-1 Aerodynamic Methods 7 Both th
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i i d .- I . ii hi L i: i t ' Li 1
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la t L I I, lj ir 1 Li c I L L' B-1
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i; 1 t u 1 1 B-3 Table 8.5. Reactor
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Table 6-7. Marginal Costs of U308 a
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LJ L L1 a .E 4' P Y W 5 18 2 16 : 0
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Appendix C. DETAILED RESULTS FROM E
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1 i; Li b L lkd t L L I hd I ' L; i
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L c-5 The introduction of the class
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i ' ibd 1 b i L L i L I Li . . b b
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Qulatiw klur W i t y hilt (*I thrmg
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L c c b - i ii L r D-1 Appendix D.
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L L L L [i i” Table D -2. Maximum
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Fig. D-2 (cont.) 25W I I I I I (I)
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[i energy center. It can be seen fr
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L L i il L t W 0-9 Table D-4. Summa
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-- Lid c i' .- .b) i Internal Distr
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It e L L L t u I' f ' ki Federal Ag
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u 1' 1" Outside Organizations (cont
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