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Title: Modular system for probabilistic fracture mechanics analysis of embrittled reactor pressure vessels in the Grizzly code

Journal Article · · Nuclear Engineering and Design
ORCiD logo [1];  [1];  [2]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Univ. of Tennessee, Knoxville, TN (United States)
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In light water reactor (LWR) nuclear power plants, the reactor pressure vessel (RPV) plays an essential safety role, and its integrity must be ensured during a variety of transient loading conditions. These can include off-normal conditions such as a pressurized thermal shock (PTS), as well as transients encountered during normal startup, shutdown, and testing of the reactor. Exposure to irradiation and elevated temperatures embrittles the RPV’s steel over time, making it increasingly susceptible to failure due to propagation of fractures that could initiate at the locations of flaws introduced during the manufacturing process. As long-term operation scenarios are being considered for LWRs in the United States, it is important to have a flexible simulation tool that can be used to perform probabilistic evaluations of RPV integrity under a wide variety of conditions and incorporate improved predictive models of RPV steel embrittlement. The Grizzly code is being developed to meet these needs. This paper describes Grizzly’s modular architecture, provides results of benchmarking studies of various components of Grizzly, and demonstrates the application of Grizzly on a model that includes plume effects that are difficult to represent in other codes being used in current practice.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1605209
Alternate ID(s):
OSTI ID: 1636046
Report Number(s):
INL-JOU-18-45783-Rev000; TRN: US2104398
Journal Information:
Nuclear Engineering and Design, Vol. 341, Issue C; ISSN 0029-5493
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 10 works
Citation information provided by
Web of Science

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
42 ENGINEERING
Reactor Pressure Vessel
Probabilistic Fracture Mechanics
Embrittlement
Grizzly