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WIPP: Lessons in transportation safety
As part of a future consent-based approach by the federal government to site new deep geologic repositories for nuclear waste, local communities and states that are considering hosting such facilities are sure to have many questions. Currently, the Waste Isolation Pilot Plant in New Mexico is the only example of such a repository in operation, and it offers the opportunity for state and local officials to visit and judge for themselves the risks and benefits of hosting a similar facility. But its history can also provide lessons for these officials, particularly the political process leading up to the opening of WIPP, the safety of WIPP operations and transportation of waste from generator facilities to the site, and the economic impacts the project has had on the local area of Carlsbad, as well as the rest of the state of New Mexico.
E.T. Cheng
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 489-495
Nonelectrical Applications | doi.org/10.13182/FST98-A11963660
Articles are hosted by Taylor and Francis Online.
The ST-VNS devices designed for testing and developing fusion power blanket may offer a unique opportunity for near-term, non-electric applications:
-A minimum size, MW level, plasma based 14 MeV neutron source can be very attractive for neutron science applications such as neutron and gamma radiography, and isotope production.-A 70–250 MW level ST-VNS can provide neutrons to drive a sub-critical fission assembly to destroy the actinides discharged from about 10–30 light water reactors and to produce power. A further reduction of long-term radiological hazard from fission power plants can be assured when additional 1,000 – 3,000 MW fusion reactors are developed in the future to transmute the long-lived fission products, Tc and I.-The ST-VNS device also offers a possibility to produce tritium for industrial and defense applications. A 300 MW spin-off device is capable of producing an excess tritium of 2 kg annually, when a conservative overall tritium breeding ratio of 1.2 and 60% availability are assumed.
A minimum size, MW level, plasma based 14 MeV neutron source can be very attractive for neutron science applications such as neutron and gamma radiography, and isotope production.
A 70–250 MW level ST-VNS can provide neutrons to drive a sub-critical fission assembly to destroy the actinides discharged from about 10–30 light water reactors and to produce power. A further reduction of long-term radiological hazard from fission power plants can be assured when additional 1,000 – 3,000 MW fusion reactors are developed in the future to transmute the long-lived fission products, Tc and I.
The ST-VNS device also offers a possibility to produce tritium for industrial and defense applications. A 300 MW spin-off device is capable of producing an excess tritium of 2 kg annually, when a conservative overall tritium breeding ratio of 1.2 and 60% availability are assumed.
