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Title: Dynamic event tree analysis with the SAS4A/SASSYS-1 safety analysis code

Journal Article · · Annals of Nuclear Energy (Oxford)
 [1];  [2];  [3]
  1. The Ohio State Univ., Columbus, OH (United States). Nuclear Engineering Program; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Risk & Reliability Analysis
  2. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Risk & Reliability Analysis
  3. The Ohio State Univ., Columbus, OH (United States). Nuclear Engineering Program

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. Finally, newly-developed dynamic importance measures are used to assess the significance of reactor parameters/constituents on calculated consequences of initiating events.

Research Organization:
Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)
Grant/Contract Number:
AC04-94AL85000; NA0003525
OSTI ID:
1431214
Report Number(s):
SAND--2018-2366J; 661558
Journal Information:
Annals of Nuclear Energy (Oxford), Journal Name: Annals of Nuclear Energy (Oxford) Journal Issue: C Vol. 115; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English