Can someone pls explain, page-5

cj-lie-bs the link below is from the US Government library technical publications, it was written by J.Stephen. Herring from the Idaho National Laboratory, The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance,

www.inl.gov/technicalpublications/Documents/5869830.pdf

Does what is written in this document sound like LIS doesn't work or Silex in particular because it specifically mentions the Silex process?
In fact it shows that the Laser separation can also be used for far more than just Uranium, it can separate out specific Isotopes, which is something that no other technology has been capable of doing before this, especially centrifuge, because that uses a completely different method of separation, the Silex system is the only proven method but I believe there is also another one now called MAGNIS, whether it is capable of competing with Silex is not clear at this point.

Please stop trying to spread lies and BS, stick to the proven facts.

Abstract
The future of nuclear energy and its ability to fulfill part of the world’s energy needs for centuries to come depend on a reliable input of nuclear fuel, either thorium or uranium.
Obviously, the present nuclear fuel cycle is completely dependent on uranium. Future thorium cycles will also depend on 235U or fissile isotopes separated from used fuel to breed 232Th into fissile 233U.

Finally, the evolving technologies for laser isotope separation are indicating methods for reducing the energy input to uranium enrichment but also for tailoring the isotopic vectors of fuels, burnable poisons and structural materials, thereby adding another tool for dealing with long-term
waste management.

The SILEX process was developed in Australia, beginning in 1988. In 2007 Silex Systems signed an exclusive agreement with General Electric for commercialization and licensing of the process in Wilmington, NC under the name Global Laser Enrichment (GLE).
The present partners in GLE are GE, Hitachi and Cameco. On September 19, 2012 the NRC granted a permit for GLE to build a commercial plant which would enrich uranium to a maximum of 8 % 235U.
GLE plans to build an initial 1MSWU/year module and to expand the plant in stages to 6 MSWU/year.
The initial attraction for laser isotope separation is its lower (though proprietary) energy demand.
Because of the isotope-specific nature of the excitation, LIS is capable of selecting a single middle isotope from a mixture.
For instance, LIS could remove the 236U from a mixture of 235U, 236U and 238U. Niki et al.21 have demonstrated the enrichment of natural Gd to 90% 157Gd using a combination of lasers for excitation and ionization.
The 157Gd, with an absorption cross section of 255,000 b, is to be used as a burnable poison in LWRs.
And Forsberg22 has explored the impact of separating 240Pu for the mixture of plutonium isotopes in used nuclear fuel.
While this concept poses several severe technical challenges in the development of the appropriate LIS system and its integration into the reprocessing, the removal of the 240Pu significantly decreases the subsequent production of minor actinides.

Conclusion
Enrichment using laser isotope separation may be less expensive per SWU due to its lower energy requirements.
That improvement, in turn, would allow the tails assay to be decreased, thus
requiring less natural uranium feed per kg of fuel.
In addition, the unique characteristics of LIS would allow the selective removal of particular isotopes from recycled fuel, avoiding later actinides production.
Finally, LIS is being adapted for the tailoring of burnable poisons and structural materials to improve fuel and reactor performance.