ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
The RAIN scale: A good intention that falls short
Radiation protection specialists agree that clear communication of radiation risks remains a vexing challenge that cannot be solved solely by finding new ways to convey technical information.
Earlier this year, an article in Nuclear News described a new radiation risk communication tool, known as the Radiation Index, or, RAIN (“Let it RAIN: A new approach to radiation communication,” NN, Jan. 2025, p. 36). The authors of the article created the RAIN scale to improve radiation risk communication to the general public who are not well-versed in important aspects of radiation exposures, including radiation dose quantities, units, and values; associated health consequences; and the benefits derived from radiation exposures.
Peter Hofmann, Siegfried J. L. Hagen, Volker Noack, Gerhard Schanz, Leo K. Sepold
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 200-224
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT118-200
Articles are hosted by Taylor and Francis Online.
Integral experiments with 2-m-long pressurized water reactor and boiling water reactor fuel rod bundle simulators containing a maximum of 57 rods (the CORA experimental program) as well as comprehensive single-effects investigations are examined. The physico-chemical material behavior of light water reactor fuel elements up to ∼2700 K under flowing steam is described. Of particular importance is the determination of critical temperatures above which liquid phases form as a result of chemical interactions between the fuel element components and their influence on damage propagation. The results of the experiments show that low-temperature liquid phases form as early as ∼1300 K as a result of chemical interactions of INCONEL grid spacers with the Zircaloy cladding tube, of the absorber materials (Ag-In-Cd) with Zircaloy, and of boron carbide with stainless steel; however, extensive propagation of these interactions over large distances occurs only above 1550 K. Uranium oxide (UO2) fuel can be liquefied (dissolved) by molten metallic Zircaloy, with the formation of a U-Zr-O melt resulting in UO2 relocation. This process can even take place below the melting point of Zircaloy (2040 K) if the melt, generated by chemical reactions with the various core components, contains metallic zirconium. Beyond the melting point of Zircaloy (≥2040 K), the metallic melt dissolves UO2 more strongly; i.e., at a given time, more UO2 is dissolved. In this case, UO2 relocation occurs ∼1000 K below its melting point. The molten materials form coolant channel blockages (crusts) on solidification. In the CORA experimental facility, temperatures necessary to melt the remaining solid ceramic materials, up to ∼3150 K (according to the U-Zr-O phase diagram), were not attained. On the basis of the experimental results and thermodynamic considerations, three distinct temperature regimes can be defined where liquid phases that form in the reactor core give rise to substantial material relocations and different degrees of core damage. Quenching of an overheated fuel element with water from the bottom (simulating flooding of an uncovered reactor core) initially gives rise to further heating of the bundle components as a result of intensive oxidation of metallic constituents, which is associated with the formation of local melts and the additional generation of considerable amounts of hydrogen within a very short period of time.