Advanced SearchSearch Tips
Identification of the Most Conservative Condition for the Safety Analysis of a Nuclear Power Plant by Use of Random Sampling
facebook(new window)  Pirnt(new window) E-mail(new window) Excel Download
 Title & Authors
Identification of the Most Conservative Condition for the Safety Analysis of a Nuclear Power Plant by Use of Random Sampling
Jeong, Hae-Yong;
  PDF(new window)
For the evaluation of safety margin of a nuclear power plant using a conservative methodology, the influence of applied assumptions such as initial conditions and boundary conditions needs to be assessed deliberately. Usually, a combination of the most conservative initial conditions is determined, and the safety margin for the transient is evaluated through the analysis for this conservative conditions. In existing conservative methodologies, a most-conservative condition is searched through the analyses for the maximum, minimum, and nominal values of the major parameters. In the present study, we investigates a new approach which can be applied to choose a most-conservative initial condition effectively when a best-estimate computer code and a conservative evaluation methodology are utilized for the evaluation of safety margin of transients. By constituting the band of various initial conditions using the random sampling of input parameters, the sensitivity study for various parameters are performed systematically. A method of sampling the value of control or operation parameters for a certain range is adopted by use of MOSAIQUE program, which enables to minimize the efforts for achieving the steady-state for various different conditions. A representative control parameter is identified, which governs the reactor coolant flow rate, pressurizer pressure, pressurizer level, and steam generator level, respectively. It is shown that an appropriate distribution of input parameter is obtained by adjusting the range and distribution of the control parameter.
evaluation methodology;safety analysis;safety margin;initial conditions;random sampling;
 Cited by
IAEA, Safety Margins of Operating Reactors: Analysis of Uncertainties and Implications for Decision Making, IAEA-TECDOC-1332, IAEA, 2003.

IAEA, Deterministic Safety Analyses for Nuclear Power Plants, IAEA Safety Standards Series No. SSG-2, IAEA, Vienna, 2009.

KHNP, Korea Non-LOCA Analysis Package, TR-KHNP-0009, 2007 (in Korean).

C. Jang and K. Um, Applications of Integrated Safety Analysis Methodology to Reload Safety Evaluation, Nuclear Engineering and Technology, Vol. 43, No. 2, 2011.

KHNP Nuclear Power Education Institute, Nuclear Systems Fundamental III, 2004 (in Korean).

KAERI, MOSAIQUE Users Guide, Korea Atomic Energy Research Institute, 2014.

H.-Y. Jeong and M.-G. Park, Determination of Initial Conditions for the Safety Analysis by Random Sampling of Operating Parameters, Tran. KNS Spring Meeting, 2015.