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NRC looks to leverage previous approvals for large LWRs
During this time of resurging interest in nuclear power, many conversations have centered on one fundamental problem: Electricity is needed now, but nuclear projects (in recent decades) have taken many years to get permitted and built.
In the past few years, a bevy of new strategies have been pursued to fix this problem. Workforce programs that seek to laterally transition skilled people from other industries, plans to reuse the transmission infrastructure at shuttered coal sites, efforts to restart plants like Palisades or Duane Arnold, new reactor designs that build on the legacy of research done in the early days of atomic power—all of these plans share a common throughline: leveraging work already done instead of starting over from square one to get new plants designed and built.
Charles Forsberg
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 63-70
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-137
Articles are hosted by Taylor and Francis Online.
Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation creating a new unexplored dimension in fuel cycle options. This may have large impacts on light water reactor (LWR) closed fuel cycles and waste management. If 240Pu is removed before recycling plutonium as mixed-oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, americium, and curium. Plutonium-240 is a fertile material and thus can be replaced by 238U. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Reducing production of 241Pu by removal of 240Pu reduces production of 241Am—the primary heat generator in spent nuclear fuel after several decades. Reducing heat-generating 241Am would reduce repository size, cost, and waste toxicity. Avoiding 241Am avoids its decay product 237Np, a nuclide that partly controls long-term oxidizing repository performance. The 240Pu could be added to the high-level waste for disposal. Some of these benefits also apply to plutonium recycled into fast reactors. However, the benefits are fewer because in a fast neutron spectrum, 240Pu is both a fissile material and a fertile material. There would be incentives to separate 242Pu and dispose of it as a waste.