Summary of modified 9Cr-1Mo steel development program, 1975-1985

DiStefano, J.R.; Sikka, V.K.; Blass, J.J.; Brinkman, C.R.; Corum, J.M.; Horak, J.; Huddleston, Rob; King, J. F.; McClung, R.W.; K, Sartory, W

doi:10.2172/712852

Cited by 26 publications

(29 citation statements)

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“…At the conclusion of the development, the chemical composition as shown in Table 1 was recommended for commercialization. The recommended commercialization composition included an aim value and an allowed range for each element [2]. Depending on product forms, the chemistry of the ASTM and ASME specifications has slight variations from that in Table 1.…”

Section: Methodsmentioning

confidence: 99%

“…Fig. 5 clearly demonstrates that with S m as the base for the reference stress, the negligible creep curve developed from the time fraction criterion, Equation (1), is different from, but comparable to that developed from the strain criterion, Equation (2). …”

mentioning

confidence: 88%

“…It is considered an acceptable practice for T-1324 Test No. A-3 under T-1300 "Deformation and Strain Limits for Structural Integrity" that a detailed creep-fatigue evaluation is not required if the limits of the test, as shown in Equation (1) and Equation (2), are satisfied. In other words, the creep effects can be deemed negligible.…”

Section: Evaluation and Development Of Negligible Creep Criteriamentioning

confidence: 99%

“…2. To provide a convenient tool for evaluating negligible creep in Grade 91, a negligible creep curve should be developed using Equation (1) or Equation (2). To use Equation (1), 1.5S y |T i in Table 4 and Table 5 is first employed to determine the value of t id from Fig.…”

mentioning

confidence: 99%

“…The negligible creep curve is developed and compared in Fig. 5 with that derived from Equation (2). Again, the lowest portion is extrapolated as indicated in brown.…”

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confidence: 99%

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Assessment of Negligible Creep, Off-Normal Welding and Heat Treatment of Gr91 Steel for Nuclear Reactor Pressure Vessel Application

Ren¹,

Terry²

2006

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ABTRACTTwo different topics of Grade 91 steel are investigated for Gen IV nuclear reactor pressure vessel application. On the first topic, negligible creep of Grade 91 is investigated with the motivation to design the reactor pressure vessel in negligible creep regime and eliminate costly surveillance programs during the reactor operation. Available negligible creep criteria and creep strain laws are reviewed, and new data needs are evaluated. It is concluded that modifications of the existing criteria and laws, together with their associated parameters, are needed before they can be reliably applied to Grade 91 for negligible creep prediction and reactor pressure vessel design. On the second topic, effects of off-normal welding and heat treatment on creep behavior of Grade 91 are studied with the motivation to better define the control over the parameters in welding and heat treatment procedures. The study is focused on off-normal austenitizing temperatures and improper cooling after welding but prior to post-weld heat treatment.

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Section: Methodsmentioning

confidence: 99%

mentioning

confidence: 88%

Section: Evaluation and Development Of Negligible Creep Criteriamentioning

confidence: 99%

mentioning

confidence: 99%

“…The negligible creep curve is developed and compared in Fig. 5 with that derived from Equation (2). Again, the lowest portion is extrapolated as indicated in brown.…”

mentioning

confidence: 99%

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