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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, R.J. Cerbone, Y.-K.M. Peng, J.D. Galambos, D. Strickler, I.N. Sviatoslavsky, C.P.C. Wong, D.K. Sze, X.R. Wang, M. Simnad, M. Tillack
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 1066-1070
Nuclear Testing and Design (Poster Session) | doi.org/10.13182/FST98-A11963755
Articles are hosted by Taylor and Francis Online.
Progress is given on the investigation of a low cost, scientifically attractive, and technologically feasible volumetric neutron source (VNS) based on the spherical torus (ST) concept. The ST-VNS has a major radius of 1.07 m, an aspect ratio of 1.4, and a plasma elongation 3. It can produce a neutron wall loading ultimately up to 5 MW/m2 averaged over the outboard test section when the fusion power reaches 380 MW. Initial operation of this device can be at a level of 1 MW/m2 or lower. Higher performance blanket components can be developed to raised the neutron wall loading. Using staged high wall loading operation scheme and optimistic availability projected for the VNS device, a neutron fluence of more than 30 MW-y/m2 can be expected to accumulate within 20 years of operation. Assessments of lifetime and reliability of fusion core components will thus be allowed in a power reactor relevant environment. A full-function testing of fusion core components may also become possible because of the high neutron wall loading capability. Integrated testing of tritium breeding in such a full scale power reactor relevant VNS device can be very useful to verify the self-sufficiency of fuel cycle in candidate power blanket concepts.