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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
Hisao Yamakoshi
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 152-180
Technical Paper | doi.org/10.13182/NSE84-A17709
Articles are hosted by Taylor and Francis Online.
By introducing a concept of shielding characteristics, a new method is proposed for shielding calculations of spent fuel shipping casks. The method separates ordinary shielding calculation into two steps, one calculates the radiation current leaking from the unshielded cavity region. The other method synthesizes the radiation dose rate outside the cask arising from the leaked current, the response functions for the radiation dose rate at the outer cask surface, and the functions for the radiation current reflected from the inner surface of the cask wall. In the synthesis, the effect of the coupling of the currents reflected between the cask wall and the cavity region is taken into account. The validity of the proposed method is confirmed by applying the method to an analysis of the measured data obtained for a CRIEPI cask. Response functions, the established characteristic functions for radiation shielding capabilities, are calculated for several typical actual casks. Calculated results are summarized for the convenience of applying the proposed method to actual cases. The merits of the present study are (a) the calculational code of the proposed method deals with only matrix calculations in short-step programming and is suitable for a microcomputer for which input data of characteristic functions are supplied from floppy disks, (b) with large and high-speed computers, one can evaluate radiation dose rates on the outer surface of a given cask in very short machine time and with good accuracy, (c) by application of the characteristic functions, one can extract information that will improve the design of the cask walls to provide more effective shielding by intercomparison of characteristic functions for several types of casks, and (d) one can foresee the influence of changes in the energy spectrum of source radiations on the neutron and the gamma-ray dose rates at the outer cask surface by the rule-of-thumb of superimposing the characteristic functions of the dose rate because they are functions of the incident energies.
