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Front-end nuclear fuel supply cooperation: Turning allied interdependence into strategic advantage
The global nuclear revival, which is fueled by unprecedented demand for firm, affordable, dispatchable power for artificial intelligence and data center build-out, energy security imperatives, and climate commitments, has exposed a structural reality of the Western fuel cycle: No single allied nation currently possesses the full suite of front-end capabilities. From mining through conversion, enrichment, fabrication, and the emerging deconversion and metallization steps required for reactor fuels, capability is distributed across Canada, France, Japan, the United Kingdom, and the United States (collectively, the “Sapporo Five”), as well as a small group of close partners.
A. J. Buslik
Nuclear Science and Engineering | Volume 35 | Number 3 | March 1969 | Pages 303-318
Technical Paper | doi.org/10.13182/NSE69-A20009
Articles are hosted by Taylor and Francis Online.
A self-adjoint positive-definite variational principle is presented which leads to upper and lower bounds for < S*, ϕ >, where < S*, ϕ > is an integral over position and angular direction of the product of the one-velocity neutron transport flux, ϕ and an arbitrary adjoint source, S*. The Euler equation of the functional is a new form of the one-velocity Boltzmann neutron transport equation in which the dependent variable is one-half the sum of ϕ and ϕ*, where ϕ* is the adjoint flux. When a trial function consisting of an expansion in spherical harmonics is used, one obtains as a lower bound for < S*, ϕ > the quantity < US1, ϕ(P−N′; S1) > − < US2, ϕ(P−N″; S2) >, where S1(r, Ω) = [S(r, Ω) + S*(r, −Ω)]/2, S2(r, Ω) = [S(r, Ω) − S*(r, −Ω)]/2, ϕ(P-N′; S1) is an odd P−N approximation to a problem with the same cross sections as the original problem, but with source S1; ϕ(P−N″; S2) is an even P−N approximation to a problem with source S2, and U is the operator that takes a function f(r, Ω) into f(r, −Ω).