Journal
ANNALS OF NUCLEAR ENERGY
Volume 115, Issue -, Pages 55-72Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2018.01.001
Keywords
ADAPT; SAS4A/SASSYS-1; SFR; DET; Dynamic PRA; Transient overpower
Categories
Funding
- U.S. Department of Energy's National Nuclear Security Administration [DE-NA-0003525]
- SNL Laboratory Directed Research and Development program
- Advanced Reactor Concepts program at the U.S. Department of Energy's Office of Nuclear Energy [SAS4A/SASSYS-1]
Ask authors/readers for more resources
The consequences of a transient in an advanced sodium-cooled fast reactor are difficult to capture with the traditional approach to probabilistic risk assessment (PRA). Numerous safety-relevant systems are passive and may have operational states that cannot be represented by binary success or failure. In addition, the specific order and timing of events may be crucial which necessitates the use of dynamic PRA tools such as ADAPT. The modifications to the SAS4A/SASSYS-1 sodium-cooled fast reactor safety analysis code for linking it to ADAPT to perform a dynamic PRA are described. A test case is used to demonstrate the linking process and to illustrate the type of insights that may be gained with this process. Newly developed dynamic importance measures are used to assess the significance of reactor parameters/constituents on calculated consequences of initiating events. (C) 2018 Elsevier Ltd. All rights reserved.
Authors
I am an author on this paper
Click your name to claim this paper and add it to your profile.
Reviews
Recommended
No Data Available