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
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
NRC approves V.C. Summer’s second license renewal
Dominion Energy’s V.C. Summer nuclear power plant, in Jenkinsville, S.C., has been authorized to operate for 80 years, until August 2062, following the renewal of its operating license by the Nuclear Regulatory Commission for a second time.
Chun-Sheng Chien, Shih-Jen Wang, Te-Chuan Wang
Nuclear Technology | Volume 119 | Number 2 | August 1997 | Pages 194-200
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35386
Articles are hosted by Taylor and Francis Online.
The MELCOR code is a severe accident analysis code for nuclear power plants. The steam generator dryout time in a station blackout (SBO) accident, which depends on the initial water inventory, is an important parameter in probabilistic risk assessment. Furthermore, the plant transient responses are strongly affected by the initial conditions. To simulate a consistent accident scenario with MELCOR, a correct initial steady-state condition must be generated. However, the current MELCOR users’ manual does not provide a self-initialization procedure. It is quite difficult to achieve the desired initial conditions through a trial-and-error approach. A MELCOR self-initialization algorithm for pressurized water reactor (PWR) plants and its importance in accident analysis is described. First, a MELCOR self-initialization algorithm for a PWR plant is developed and implemented with control functions provided in MELCOR; this is just an input feature in preparing the MELCOR input deck. The initialization work at full-power conditions of the Maanshan nuclear power station is cited as an example. These initial conditions are successfully generated within 50 s with the developed algorithm. Then, the initial responses and the predicted steam generator dryout time in an SBO accident are used to demonstrate the importance of the self-initialization algorithm. This algorithm provides the MELCOR users with a convenient initialization methodology and improves the simulation accuracy.