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Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
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.