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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
Michael J. Kolar, Nolan C. Olson
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 56-64
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31958
Articles are hosted by Taylor and Francis Online.
A mathematical model was developed to calculate the dose to equipment inside containment of power reactors following a maximum hypothetical accident (MHA). The model permitted both instantaneous and time-dependent releases and incorporated decay chains up to six isotopes in length. The release of noble gases produced by the decay of halogens that plate out on surfaces or are trapped by filters was taken into account. The resulting equations were solved analytically. The gamma and beta dose due to an MHA from a 3-GW(th) reactor was computed using this model. Results show that the use of decay chains produces a 38% increase in dose, and an instantaneous release produces a dose that is 14% higher than the time-dependent release.