Fracture Toughness Properties of Tritium Charged and Aged Stainless Steels: SRNL and SNL Collaboration Test Plan and 2018 Results

Krentz, Timothy; Hitchcock, Dale; Morgan, Michael; Ronevich, Joseph Allen; Sills, Ryan B.; Marchi, Chris San; Balch, Dorian K.

doi:10.2172/1630269

Cited by 4 publications

(6 citation statements)

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“…Tritium embrittlement has been studied at SRNL through tensile and fracture testing of austenitic stainless steel base metal forgings, providing necessary inputs for design guidance [6,7]. These data, combined with testing at SNL/CA on hydrogen-precharged materials, have provided the basis of our current understanding of hydrogen-isotope embrittlement.…”

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confidence: 99%

2020 Report - SRNL Aging and Lifetimes program tritium aging studies on structural alloys

Krentz

2021

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Joe Ronevich of Sandia National Laboratories prepared and provided the weld and HAZ specimens as well as the tensile and tube specimens for tritium pre-charging. He also provided results on hydrogen exposed samples of the weld and HAZ specimens, as well as valuable technical discussion and feedback. Vanessa Cofer and Kellie Holland performed vital Material Control and Accountability assistance. Chad Sweeney, Lane Rogers, Calvin Clamp, Anne Kelly, Dante Pilgrim, and Mauricio Martinez made invaluable contributions in preparing tritium charging vessels and tritium charging procedures; conducting specimen recovery; and transporting specimens to SRNL after tritium precharging runs. Dale Hitchcock and Dustin Olson conducted the TPD measurements, and Dale Hitchcock also provided valuable technical review.

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Section: List Of Tablesmentioning

confidence: 99%

2020 Report - SRNL Aging and Lifetimes program tritium aging studies on structural alloys

Krentz

2021

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“…These samples mark the start of a series of test programs laid out in SRNL-STI-2019-00022. [9] Included in this charging were three specimen geometries: 1) tubes with various heat treatment history, 2) smooth tensile, and 3) notched tensile specimens. These samples are all of type 304L stainless steel.…”

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confidence: 99%

2019 accomplishments: degradation of mechanical properties in structural metals and welds for FTS reservoirs

Krentz

Hitchcock

2020

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This report documents work in 2019 at SRNL in support of the Aging and Lifetimes program. Specimens for fracture toughness testing were prepared in prior years by thermally pre-charging samples, provided by Sandia National Laboratories, of welded types 304L and 21-6-9 stainless steels. These samples were precharged in 2017. The fracture toughness of the first aged specimens was measured and compared to historical data. The measurements of the 304L and 21-6-9 weld and particularly HAZ represent some of the first fracture data relevant to modern GTS reservoirs. This work represents an on-going collaboration between SRNL and SNL to understand tritium embrittlement of structural metals in Gas Transfer System reservoirs which informs lifetime assessments.Continued testing was conducted on ongoing historical studies, including the effects of very long-term aging, and the relative performance of differently forged stockpile relevant 304L and 316L samples.

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“…Tritium embrittlement has been studied at SRNL through tensile and fracture testing of austenitic stainless steel base metal forgings, providing necessary inputs for design guidance [6,7]. These historical studies progressed from examinations of representative materials, to actual stockpile forgings, and variations on forging techniques as well as joining technologies.…”

Section: Introductionmentioning

confidence: 99%

“…These ongoing studies build on the above-mentioned historical studies, and those studies progressed from representative material studies to realistic engineering studies on forgings and joining technology, these studies take a strategy of meeting the current data requirements necessitated by changing manufacturing technologies and progressing on to fundamental science which deepens understanding of the mechanics of materials after tritium exposure. Prospective future studies were laid out in [7].…”

Section: Introductionmentioning

confidence: 99%

“…Figure 3-6 -Engineering stress strain curves from 3 tests with EB weld material thermally precharged with nominally 3700 appm tritium and aged to develop nominally 100 appm of helium 3.5 Tensile testing of Annealed 21-6-9 material Previous reports (Annual aging studies report SRNL-STI-2018-00036[7], and SRNL-STI-2020-00002[16]) discussed the preparation and initial fracture testing results from tritium-pre-charged 304L/308L FZ and HAZ and 21-6-9/308L FZ and HAZ samples. Longer aging conditions were tested in 2020 in the same fashion as reported in those previous documents, at approximately 3 years of aging, leading to nominally 600 and 980 appm helium in the 304L and 21-6-9 samples respectively.…”

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2021 Report - SRNL Aging and Lifetimes program tritium aging studies on structural alloys

Krentz¹,

MULLINS²

2022

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Fracture Toughness Properties of Tritium Charged and Aged Stainless Steels: SRNL and SNL Collaboration Test Plan and 2018 Results

Cited by 4 publications

References 15 publications

2020 Report - SRNL Aging and Lifetimes program tritium aging studies on structural alloys

2020 Report - SRNL Aging and Lifetimes program tritium aging studies on structural alloys

2019 accomplishments: degradation of mechanical properties in structural metals and welds for FTS reservoirs

2021 Report - SRNL Aging and Lifetimes program tritium aging studies on structural alloys

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