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Nuclear Nonproliferation Policy
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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Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
J. Richard Smith, John J. King
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1925-1930
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29623
Articles are hosted by Taylor and Francis Online.
Neutron multiplication occurs in beryllium because of the high (n, 2n) cross section. On the basis of calculations made using microscopic nuclear data, multiplication in a beryllium blanket should improve the efficiency of a tritium breeder. Previous experiments have indicated that the net multiplication is too low for beryllium to be an effective neutron multiplier. It seemed appropriate to make a further study of the multiplication of 14-MeV neutrons in bulk beryllium, utilizing the superior isotropy and flat energy response of the manganese bath. In the manganese bath method a 14-MeV neutron source is placed at the center of a large tank containing an aqueous solution of MnSO4. With a beryllium sample surrounding the neutron source in the sample chamber, the neutrons first multiply in beryllium and produce in the manganese bath an activity proportional to the source rate times the multiplication factor. The ratio of the “sample-in” and the “open beam” activities is the raw value of the multiplication. Several systematic corrections must then be applied to deduce the true multiplication in beryllium. Uncorrected values of the multiplication have been obtained for beryllium samples of four thicknesses. For beryllium thicknesses of 4.6, 12.0, 15.6, and 19.9 cm the multiplication values are 1.399, 1.928, 2.072, and 2.126, respectively. These values are affected by several systematic effects characteristic of the manganese bath. The values of these systematic corrections are established by a combination of calculation and experimental parameterization. The detailed calculations use the Monte Carlo program MCNP. The experimental values are in good agreement with those calculated from microscopic cross sections.
