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

Spencer, B. W.; Hoffman, W. M.; Backman, M. L.

doi:10.1016/j.nucengdes.2018.10.015

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

Journal Article · Mon Oct 29 00:00:00 EDT 2018 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2018.10.015· OSTI ID:1605209

^[1]; Hoffman, W. M. ^[1]; Backman, M. L. ^[2]

Idaho National Lab. (INL), Idaho Falls, ID (United States)
Univ. of Tennessee, Knoxville, TN (United States)

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.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE; USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1605209

Alternate ID(s):: OSTI ID: 1636046
OSTI ID: 22893856

Report Number(s):: INL-JOU--18-45783-Rev000

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: C Vol. 341; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Related Subjects

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

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

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