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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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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.
John N. Hamawi
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 363-370
Technical Note | doi.org/10.13182/NT16-18
Articles are hosted by Taylor and Francis Online.
Estimates of radiation doses to receptors in the vicinity of nuclear power plants from gaseous effluents are important to ensure that plant operation is in compliance with the as-low-as-reasonably-achievable dose objectives delineated in 10 CFR 50, Appendix I. The U.S. Nuclear Regulatory Commission (NRC) recently issued an Advance Notice of Proposed Rulemaking (ANPR) on the development of a new regulatory basis in support of aligning the NRC regulations governing dose assessments for radioactive effluents with the most recent methodology published by the International Commission on Radiological Protection (ICRP) contained in ICRP Publication 103 (ICRP-103) (2007). The ANPR specifically recommends that the dose conversion factors (DCFs) in Regulatory Guide 1.109 (RG 1.109) be revised as part of any effort to more closely align the NRC’s regulations with the ICRP-103 recommendations. Section C.2 of RG 1.109 provides a sector-average (SA) finite-cloud model for computation of annual doses at off-site receptors from noble gas releases from freestanding tall stacks. One of the limitations of this model is that embedded in the applicable equation is the DCF, and as such, the model is not suitable for implementation of the ANPR (if approved) and the recommended use of stand-alone updated DCFs. This limitation can be circumvented through use of the “gamma atmospheric dispersion factor” in the finite-cloud dose model, referred to as the gamma (χ/Q). A second limitation of the SA finite-cloud model is the dose overestimation at close-in receptors under very stable conditions and elevated plumes, which can be eliminated by using the corresponding finite-cloud gamma (χ/Q) for the plume-centerline (PC) model. Presented are analytical details on the derivation and use of the SA and PC gamma (χ/Q)’s, which are suitable for incorporation of stand-alone updated sets of DCFs based on ICRP-103.
