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The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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Retrieval of nuclear waste canisters from a borehole
Borehole disposal of spent nuclear fuel (SNF) and high-level waste (HLW) uses off-the-shelf directional drilling technology developed and commercialized by the oil and gas sectors. It is a technology that has been gaining traction in recent years in the nuclear industry. Disposal can be done in one or more boreholes (including an array) drilled into suitable sedimentary, igneous, or metamorphic host rocks. Waste is encapsulated in specialized corrosion-resistant canisters, which are placed end to end in disposal sections of relatively small-diameter boreholes that have been cased and fluid-filled. After emplacement, the vertical access hole is plugged and backfilled as an engineered barrier.
Takuro Honda, Takashi Okazaki, Yasushi Seki, Isao Aoki, Tomoaki Kunugi
Fusion Science and Technology | Volume 30 | Number 1 | September 1996 | Pages 95-103
Technical Paper | Safety and Environmental Aspect | doi.org/10.13182/FST96-A30766
Articles are hosted by Taylor and Francis Online.
Dust production due to plasma disruptions has been investigated using a safety analysis code, which can calculate the plasma dynamics and thermal characteristics of fusion reactor structures simultaneously. We selected two fusion reactor designs in the International Thermonuclear Experimental Reactor (ITER), i.e., the Engineering Design Activity (EDA) and the Conceptual Design Activity (CDA). The ITER/EDA will adopt beryllium for the plasma-facing component (PFC), and the ITER/CDA adopted graphite for PFC. The beryllium dust production in the ITER/EDA reactor will range from 7.0 to 10.3 kg/disruption, which strongly depends on vapor shield effects. The carbon dust production in the ITER/CDA reactor will range from 1.9 to 2.4 kg/disruption. However, the carbon dust will increase by as much as a factor of 2 to 5 because the effective latent heat of graphite has a large uncertainty under the extremely high heat flux during disruptions. For both, dust production from the first wall depends on the current quench time during disruptions. If the current quench time can be extended, the beryllium dust from the first wall will be minimized, and the carbon dust from there will be negligible.