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Procedia Engineering 86 ( 2014 ) 272 – 280

1877-7058 © 2014 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/3.0/).

Peer-review under responsibility of the Indira Gandhi Centre for Atomic Research doi: 10.1016/j.proeng.2014.11.038

ScienceDirect

1st International Conference on Structural Integrity, ICONS-2014

Application of a Cleavage Fracture Stress Model for Estimating

the ASTM E-1921 Reference Temperature of Ferritic Steels

from Instrumented Impact Test of CVN Specimens without

Precracking

P.R. Sreenivasan

Metallurgy and Materials Group, Indira Gandhi Centre for Atomic Research, Kalpakkam-603102, India E-mail ID: [email protected] or [email protected]

Abstract

A recently proposed semi-empirical cleavage fracture stress (CFS) model by the author based on the microscopic cleavage fracture stress, σf, for estimating the ASTM E-1921 reference temperature, T0, of ferritic steels from instrumented impact test (IIT) of Charpy V-notch (CVN) specimens without precracking has been demonstrated for steels with room temperature yield strength in the range 400-750 MPa, including irradiated steels. The estimate of T0, based on the CFS model, TQcfs lies within a ± 20 ºC band, being conservative for most of the steels, but less conservative than TQIGC based on the IGC-procedure. CFS model enhances the validity and utility of the CVN IIT by enabling estimation of design-relevant master curve from unprecracked CVN specimens. In this paper, the method is further applied to some steels (both unirradiated and irradiated) reported in the literature most of which have only IIT data and static tensile data available. The method has also been applied to some IIT test results obtained at IGCAR for 9Cr-1Mo steel in various simulated weld-heat affected zone conditions. The results are compared with

TQIGC or other estimates like TQBT or T0, if available. © 2014 The Authors. Published by Elsevier Ltd.

Peer-review under responsibility of the Indira Gandhi Centre for Atomic Research.

Keywords: cleavage fracture stress, instrumented impact test, reference temperature, ASTM E 1921 standard, Charpy V-notch, ferritic steels

1. Introduction

The author has, in a recent communication [1], developed a semi-empirical cleavage fracture stress (CFS) model based on the microscopic cleavage fracture stress, σf, for estimating the ASTM E-1921 reference

temperature, T0, of ferritic steels [2] from instrumented impact test (IIT) of CVN specimens without precracking.

The relevant calibration equations necessary for applying the model had been derived and demonstrated for steels

© 2014 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/3.0/).

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with room temperature yield strength in the range 400-750 MPa, including irradiated steels. However, it was concluded that the applicability and acceptability of those calibration curves for highly irradiated steels needed further examination. The estimate of T0, based on the CFS model, TQcfs (as a convention, non-standard, i.e., not

following the ASTM E 1921 standard [2] for master curve determination, estimates of T0 are designated TQ [3]), lies

within a ± 20 ºC band, being conservative for most of the steels, but less conservative than TQIGC based on the

IGC-procedure [3]. The CFS model is a single step IGC-procedure as compared to the multi-stage IGCAR-IGC-procedure and hence less error-prone due to calculational errors. However, the parameters must strictly meet the validity conditions for the calibration equations. CFS model enhances the validity and utility of the CVN IIT by enabling estimation of design-relevant master curve from unprecracked CVN specimens. Particularly relevant is the fact that the new procedure will help obtain more valuable and design relevant master curve from IIT of irradiation surveillance specimens.

The purpose of the present paper is to further apply the CFS model to some steels (both unirradiated and irradiated) reported in the literature most of which have only IIT data and static tensile data available. The method will also be applied to some test results of 9Cr-1Mo steel obtained at IGCAR in various simulated weld-heat affected zone conditions. The results will be compared with TQIGC values or other estimates or T0, if available. First

the methodology will be outlined followed by description of the material data chosen and then the final comparison will be made.

2. Methodology

2.1. Basic Outline of the Methodology

Basically, at the point of brittle fracture initiation, the local crack tip tensile stress reaches a critical value, namely, the microscopic cleavage fracture stress, ıf or ıC, (the cleavage fracture stress can be determined from

either notch-tensile tests – many authors denote this as ıC - or three-point bend or instrumented impact tests of

Charpy V-notch (CVN) specimens – mostly denoted by ıf; based on consideration of differences in sampled and

stressed volume for the two types of specimens, ıf; especially determined from instrumented impact tests, is slightly

larger than ıC from notch-tensile tests [3]) at a critical distance, usually the distance to the weakest link. In fact, a

two- or three-parameter Weibull stress distribution based on the weakest link theory is the basis of the ASTM E-1921 standard master curve also [2]. The various theoretical, semi-empirical or empirical formulations described in the literature imply that the fracture toughness variation with temperature can be expressed as a function of critical fracture stress to yield stress ratio: σf/σys or σf/σyd, where σys and σyd are the static and dynamic yield stress

respectively, the latter being determined from IIT of CVN specimens.

Based on the above considerations, the variation of the ratio, σf/σys or σf/σyd with test temperature can be

related to the corresponding static MC fracture toughness data (in the range of T0 ± 50 ºC, as ASTM E-1921 [2] MC

is valid in that range) vide, Eq. (1).

20

.exp(

) (1)

JC

K

=

+

a

by

where y = σf/σys or σf/σyd. By an iterative procedure, the constant a has been fixed as 0.366 for y = σf/σys and 1.858

for y = σf/σyd, respectively. The constant b (designated as B henceforth) has been related to σf/σys*1 and σf/σys*2

when y = σf/σys and to σf/σyd*1 and σf/σyd*2 when y = σf/σyd, respectively, where σys*1 is the σys at (T41J – 24) ºC and

σys*2 is the σys at (T41J – 50) ºC, σyd*1 is the σyd at (T41J – 24) ºC and σyd*2 is the σyd at (T41J – 50) ºC for the particular

steel. Then, there will be four B calibration curves: B1 based on σf/σys*1, B2 based on σf/σys*2, B3 based on σf/σyd*1

and B4 based on σf/σyd*2; application of B1 and B2 in the place of b in Eq. (1) (with a = 0.366) generates two sets of

MC KJC values and application of B3 and B4 in Eq. (1) (with a = 1.858) generates another two sets of MC KJC values.

The calibration curves are given below.

2 3

f f f

1

ys*1 ys*1 ys*1

-11.0557 + 11.8355

- 3.5165

+ 0.3344

(2a)

B

σ

σ

σ

σ

σ

σ

§

·

§

·

=

¨

¨

¸

¸

¨

¨

¸

¸

©

¹

©

¹

(3)

with correlation coefficient R = 0.9153 and validity range for (σf/σys*1) = 3.05 to 4.3. MC KJC data from B1 is given by: f JC 1 ys

20

0.366.exp(

) (2b)

K

B

σ

σ

=

+

2 3 f f f 2

ys*2 ys*2 ys*2

-25.8537 + 25.7755

- 7.8807

+ 0.7858

(3a)

B

σ

σ

σ

σ

σ

σ

§

·

§

·

=

¨

¨

¸

¸

¨

¨

¸

¸

©

¹

©

¹

with correlation coefficient R = 0.8525 and validity range for (σf/σys*2) = 2.8 to 3.89. MC KJC data from B2 is given

by: f JC 2 ys

20

0.366.exp(

) (3b)

K

B

σ

σ

=

+

2 3 f f f 3

yd*1 yd*1 yd*1

2.1566 + 1.1167

- 0.8441

+ 0.1263

(4a)

B

σ

σ

σ

σ

σ

σ

§

·

§

·

=

¨

¨

¸

¸

¨

¨

¸

¸

©

¹

©

¹

with correlation coefficient R = 0.8695 and validity range for (σf/σyd*1) = 2.28 to 2.995. MC KJC data from B3 is

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f JC 3 yd

20

1.858.exp(

) (4b)

K

B

σ

σ

=

+

2 3 f f f 4

yd*2 yd*2 yd*2

33.7517 - 37.5066

+ 14.713

- 1.9472

(5a)

B

σ

σ

σ

σ

σ

σ

§

·

§

·

=

¨

¨

¸

¸

¨

¨

¸

¸

©

¹

©

¹

with correlation coefficient R = 0.8334 and validity range for (σf/σyd*2) = 2.09 to 2.82. MC KJC data from B4 is given

by: f JC 4 yd

20

1.858.exp(

) (5b)

K

B

σ

σ

=

+

Estmates of T0, based on MC KJC data from Eqs. (2b), (3b), (4b) and (5b) are designated TQcfs1, TQcfs2, TQcfs3 and

TQcfs4, respectively. The criterion for choosing the estimate based on the CFS model, namely, TQcfs, is the most

conservative of the four: TQcfs1, TQcfs2, TQcfs3 and TQcfs4.

2.2. Application of the New Methodology for Estimating TQcfs

For a material with known IIT data but with no T0, T0 can be calculated by the following procedure:

i. Plot the load-temperature diagram (LTD) as in Fig.1 and determine TD.

ii. From the PF = PGY = Pmax load at TD, determine σyd at TD, using Eq. (6) andσf using Eq. (7).

iii. The dynamic yield stress of an impact three-point bend (TPB) specimen is given by Eq. (6).

yd

2.99

2

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(

)

GY

P W

B W

a

σ

=

where W = B = 10 mm and a = 2 mm for a standard (full-size) CVN specimen and PGY is in N.

The micro-cleavage fracture stress, σf is given by [15]: yd

2.52

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f

σ

=

σ

where ıyd is the value at TD..

iv. Plot the T vs. CV curve and determine (T41J – 24) ºC and (T41J – 50) ºC temperatures. In case of excessive

scatter, use a lower bound (LB) curve determined by a fit to the lowest data at various temperatures. v. Plot the T vs σys (if actual static yield stress data are not available use estimates as outlined in [1]) and T vs

σyd (PGY at various temperatures is converted to σyd using Eq. (6)) and obtain σys*1, σys*2, σyd*1 and σyd*2

and the corresponding σf/σys*1, σf/σys*2, σf/σyd*1 and σf/σyd*2 values.

vi. Plot the σf/σys and σf/σyd curves.

vii. Using the calibration equations given earlier, determine the B1, B2, B3 and B4 values corresponding to the

σf/σys*1, σf/σys*2, σf/σyd*1 and σf/σyd*2 values for the particular steel.

viii. For each B (i.e., B1, B2, B3 and B4), for selected values from the σf/σys or σf/σyd curve, as the case may be,

calculate KJC using Eq. (1) (using a spread-sheet programme this can be easily done for a column of σf/σys

or σf/σyd values corresponding to various temperatures). Since, calibration was done using MC data of

calibration steels, the generated KJC data are treated as MC curve data. Then select the KJC data in the

80-120 MPa¥m (or slightly larger or lower values as may happen for some steels) and the corresponding temperatures and apply to the multi-temperature equation due to Wallin to obtain the corresponding TQ

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4 0 min 0 5 1 min 0 1 min 0 exp{0.019( ) ( ) exp{0.019( )} 0 (8) [31 77 exp{0.019( )}] [31 77 exp{0.019( )}] i n n i i JCi i i i i i T T K K T T K T T K T T

δ

= = = − − − = − − + − − + −

¦

¦

where the Kronecker δi = 1 for valid data and 0 for non-cleavage or censored data (in the present case, take

δi = 1 always), Kmin = 20 MPa√m and Ti is the test temperature (temperature corresponding to a particular

KJC value with the corresponding σf/σys or σf/σyd ratio).

3. Material Data

The materials data used for the application of the CFS model outlined in Section 2 are given in Table 1 along with source references and strength properties and T41J temperature. Here the steels are briefly described in the

order given in Table 1. AISI 403 SS is a 12%Cr martensitic stainless steel with about 0.12%C in quenched and tempered condition. As [4] gives only CVN DBTT curve, static yield stress and KIC variation variation with

temperature, σf and σyd variation with temperature have been adapted from [1] for a similar grade steel, namely,

HT-9. The HSST SAW 51B is the submerged-arc weld of HSST-01 plate which is an ASTM A533B Grade B Class 1 steel (a Mn-Ni-Mo Steel with 0.14%C, 1.3%Mn, 0.74%Ni and 0.46%Mo). HSST SAW 51B-I (irradiated) was irradiated at 296 ºC to a fluence of 1.15*1019 n.cm-2 (E > 1MeV). 22NiMoCr37 is a well pedigreed and characterized German PWR steel

forging of A508 Cl.2 Type steel (Q&T). ASTM A302B steel is precursor of modern A533B RPV steel (Q&T). The BR3 A302B steel has slightly more Ni than the ASTM A302B steel (Q&T), and hence more radiation sensitive. The BR3 A302B steel irradiation conditions were: 260 ºC; fluence of 4.4*1019 n.cm-2 (E > 1MeV). A212B is an old plain carbon-Mn (0.28%C, 0.69%Mn) RPV steel. The A212B in the I condition was irradiated at 260 ºC to a fluence of 0.94*1019 n.cm-2 (E > 1MeV). 01Ti-1 and 05Ti-1 are HSLA steels with TiN as the main strengthening precipitate.

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JRQ is a well pedigreed A533B Gr.B Cl.1 RPV steel characterized under IAEA round-robin programme. JRQ in the I condition was irradiated at 294-301 ºC to a fluence of 4.3±0.8*1019 n.cm-2 (E > 1MeV). EUROFER is a well pedigreed 9Cr-0.12C-1W-0.19V-0.14Ta (all wt%) RAFM ferritic-martenitic steel developed for fusion reactor applications. In the I condition it was irradiated at ~300 ºC to a fluence of 1.55 dpa (approximately, 1.04*1021 n.cm-2 (E > 1MeV), a very high fluence compared to fission reactor conditions).

4. Results and Discussion

In Table 1, σf/σys*1, σf/σys*2, σf/σyd*1 and σf/σyd*2 values for each steel are also given. Some values have

been indicated in bold with underlining and they fail to meet the validity range specified for Eqs. (2a) to (5a), as the case may be. Since the equations are cubic, they produce invalid results outside their range of fit [1]. Hence, the corresponding values of TQcfsx, where ‘x’ is 1, 2, 3 or 4, as the case may be, are left blank or similarly indicated in

bold with underlining, in the results column in Table 2 (for example, for the AISI 403 SS σf/σyd*1 and σf/σyd*2 values

are indicated as invalid and hence the corresponding TQcfs3 and TQcfs4 in Table 2 are also indicated as invalid. In such

cases, the largest of the remaining valid values is taken as the TQcfs estimate.

In Table 2, for comparison, apart from T0 (where such values are available), TQIGC and TQBT values have

also been listed. TQIGC is the estimate of T0 obtained using the IGCAR procedure detailed in [3]. TQIGC values are

conservative to the extent of 20-30 ºC. TQBT is the estimate of T0 obtained from TD, the brittleness transition

temperature (see, Fig. 1). As mentioned in [3], though TQBT has a tendency to accuracy (TQBT = 1.5TD + 40 [3]), due

to various reasons, including the robustness of the TD measurement from experimental data (especially for steels

exhibiting high scatter), the estimated TQBT can be highly non-conservative as was demonstrated for two steels, 16

MND5 and HT9, in [1]. However, for the usual RPV steels and, especially, for the RAFM steels it gives very good estimates.

For the AISI 403 SS steel, the TQcfs value of -24 ºC shows excellent agreement with the T0 of -28 ºC. As is

to be expected, the TQIGC of 5.8 ºC is more conservative. These are very good when compared with the estimates for

a similar HT-9 steel reported in [1]: T41J = -18.5 ºC; T0 = -38.5 ºC; TQBT = -128 ºC; TQIGC = -33 ºC and TQcfs = -50 ºC.

As mentioned before, TQBT gives a very bad estimate here. Similar comparisons for steels with T0 in Table 2 shows

the closeness of the TQcfs values to the actual T0 with non-conservatism being less than 20 ºC and less conservatism

with respect to TQIGC values and overall better estimates than TQBT values. The only exception is the JRQ-I steel for

which TQcfs is non-conservative to the extent of 28 ºC, whereas TQIGC estimates are very good. It may be noted that

for the JRQ-I steel estimates of σf were used in the absence of IIT data. In this highly embrittled and radiation

sensitive steel, there may be more lowering of the CFS σf than that indicated resulting in non-conservative estimates

(presence of intergranular fracture can significantly affect the σf and TQcfs estimates). Especially significant is the

observation that for the highest irradiated steel in Table 2, namely, EUROFER-97, the TQcfs estimates are in

excellent agreement with T0, TQcfs and TQIGC estimates. For the other steels in Table 2 without T0 values, TQcfs and

TQIGC estimates are in better agreement with each other. One point to be noted is that for the EUROFER-I steel in

Table 2, two TQIGC estimates are given, namely, -62 ºC and 7.5 ºC, the former being unacceptably non-conservative

while the latter acceptably conservative and close to and slightly larger than the TQcfs. This is because, the

IGC-procedure given in [3] is a multi-stage IGC-procedure using less conservative or more conservative estimates for low and high transition temperature steels, respectively, the distinction being the TQSch

dy

being less than or equal to 60 ºC (TQSchdy is an estimate of dynamic reference temperature obtained from CVN tests used in the estimation of TQIGC).

For the RAFM steels, TQSch dy

limit may be , -10 ºC instead of 60 ºC as specified in [3] (for the E97-I material, TQSch dy

= -5 ºC).

For the 9Cr-1Mo simulated weld-HAZ (heat affected zone) material, the TQcfs, TQIGC and TQBT estimates are

in excellent agreement with each other, the former two being more conservative. This was also the case for a similar T-91 steel reported in [1] where estimates values were close to the actual T0. As was observed in [17,18], the BM

(base metal) is closer to the FPAGM (fine prior austenite grain material) in properties while ICR-materials (inter-critical region) are the toughest and the CPAM (coarse prior austenite grain material) being the least tough with the highest TQcfs.

Finally, in Fig. 2, the TQcfs values of the Table 1 steels are compared with TQIGC and T0 (for steels for which

such values are available). TQcfs vs. TQIGC values of about 48 steels in [1] are also plotted for comparison. The

estimate of T0, based on the present CFS model, TQcfs, lies within a ± 20 ºC band, being conservative for most of the

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steel the TQcfs value is conservative and close to T0. The trend shown by the present steels is no different from that

shown by steels reported in [1] and replotted in Fig. 2. As original calibration curves are based on unirradiated steels, the method needs further verification with results from more severely irradiated steels.

5. Conclusions

Thus, the CFS (cleavage fracture stress) model, based on the microscopic cleavage fracture stress, σf, for

estimating the ASTM E-1921 reference temperature of ferritic steels from instrumented impact test (IIT) of unprecracked CVN specimens is further confirmed by test results for additional steels. As original calibration curves are based on unirradiated steels, the method needs further verification with results from more severely irradiated steels.

Acknowledgement

The author specially thanks Dr. A. Moitra, SO-G, MTD, IGCAR for providing the IIT load-temperature data for the 9Cr-1Mo simulated HAZ material. The author acknowledges with thanks the excellent support and encouragement received from Director, MMG and Director, IGCAR, Kalpakkam, India.

References

1. Sreenivasan, P. R. (2013). Estimation of ASTM E-1921 Master Curve of Ferritic Steels from Instrumented Impact Test of CVN Specimens without Precracking. Communicated to ASTM J. Mater. Perfor. and Characterisation.

2. ASTM E1921-97. Standard test method for determination of reference temperature, T0, for ferritic steels in the

transition range. Annual Book of ASTM Standards, Vol. 03.01 (1998) pp.1060-1076. ASTM, Philadelphia, USA.

3. Sreenivasan P R. Inverse of Wallin’s relation for the effect of strain rate on the ASTM E-1921 reference temperature and its application to reference temperature estimation from Charpy tests. Nucl. Engng. and Design, 241, 2011, pp. 67-81.

4. Logsdon WA, Begley JA (1977). Upper shelf temperature dependence of fracture toughness for four low to intermediate strength ferritic steels. Engng. Fracture Mechanics; 9:461-470.

5. Stelzman WJ and Bergrenn RG (1973). Radiation Strengthening and Embrittlement in Heavy-Section Steel Plates and Welds. Report No. ORNL-4871, 20 Sept. 1973. Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA.

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7. Fabry, A,m van Walle, E., Chaouadi, R,m Wannijn, J. P., Verstrepen, A., Puzzolante, J.L., VanRansbeeck, Th., and VandeVelde, . (1993). RPV Steel Embrittlement: Damage Modelling and Micromechanics in an Engineering Perspective. In Proc. Specialist Meeting on Irradiation Embrittlement and Optimisation Annealing, Paris (20-23, Sept. 1993). Jointly Organised by OECD NEA and IAEA. Report NEA/CSNI/R(94)1, pp.275-338.

8. Tetelman, AS, Wullaert, RA, and Ireland, DR. (1971). Prediction of Variation of Variation of Fracture Toughness KIC from Small Specimen Tests. Effects Technology Report TR 71-05. Effects Technology Inc.,

Santa Barbara, California (Also presented at Conference on Practical Application of Fracture Mechanics to Pressure Vessel Technology, Institution of Mechanical Engineers (Great Britain) LondonͿ͘

9. Barsom, JM and Rolfe ST. (1970). Correlations between KIC and Charpy V-notch Test Results in the

Transition-Temperature Range. Impact Testing of Metals. ASTM STP 466, pp. 281-302. ASTM, Philadelphia, USA.

10. Fabry, A, Chaouadi, R, Puzzolante, JL, Van de Velde, J, Biemiller, EC, Rosinski, ST, and Carter, RG. (1999). Comparison of BR3 Surveillance and Vessel Plates to the Surrogate Plates Representative of the Yankee Rowe PWR Pressure Vessel. (Eds.) RK, Nanstad, Hamilton, ML, Garner, FA, and Kumar, AS. Effects of Radiation on Materials: 18th International Symposium. ASTM STP 1325, pp. 452-480. ASTM, Philadelphia, USA.

11. Wullaert, RA. (1970). Applications of the Instrumented Impact Test. Instrumented Impact Testing of Metals. ASTM STP 466, pp.148-164. . ASTM, Philadelphia, USA.

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12. Ray, A., Sivaprasad, S. and Chakrabarti, D. (2012). A Critical Grain Size Concept to Predict the Impact Transition Temperature of Ti-Microalloyed Steels. Int. J. Fract. 173: pp. 215-222.

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Table 1. (Micro) Cleavage fracture stress (CFS) and other strength properties of steels*

Steel ıys-RT

(MPa) ıf

(MPa)

T41J (0C) ıf /ıys*1 ıf /ıys*2 ıf /ıyd*1 ıf /ıyd*2

AISI 403SS [4] 678 2400b Ϯϯ 3.4582 3.3708 3.0418 2.9666 HSST-SAW-51B [5] 430 1884 ͲϱϮ 3.6797 3.4632 2.4531 2.2191 HSST-SAW-51B-I [5] 663 2084 ϱϭ 3.2012 3.0692 2.6241 2.5169 22 NiMoCr 3-7 [6,7] 422 2000b Ͳϰϯ 4.040 3.8095 2.377 2.2624 A302B (ASTM) [8-9] 524 995 ϭϴ 2.4568 2.3412 2.7038 2.5448 BR3 Plate-A302B-New

(Ni modified A302B)

[10] 477 1772

Ͳϳ͘ϱ 3.5159 2.8352 2.7012 2.5028 BR3 Plate-A302B-New-I

(Ni modified A302B)

[10] 661 1850 ϭϰϬ 2.9984 2.9553 2.8201 2.7166 A212B [11] 264 1916 Ϭ 6.4511 6.0063 2.9984 2.5581 A212B-I [11] 462 2072 ϵϬď 4.4562 4.5538 3.263 2.9142 01Ti-1 [12] 439 1913 Ͳϱϵ 3.6163 3.3979 2.9029 2.6314 O5Ti-1 [12] 274 1352 Ͳϵ͘ϱ 4.2989 3.9941 2.3782 2.1736 JRQ [13,14] 474 1873 Ͳϭϴ 3.6158 3.4367 2.6343 2.5379 JRQ-I [13] 588 1800 ϱϳ 3.2127 3.0959 2.7066 2.6050 EUROFER-97 [15,16] 557 2505 ͲϳϮ 3.8538 3.4743 2.6621 2.411 EUROFER-97-I [16] 797 2525 ϳ͘ϳ 3.1058 3.0312 2.5977 2.4373 18MND5 [16] 546 2223 Ͳϲϲ 3.6744 3.3682 2.7997 2.4978

9Cr-1Mo Steel Simulated Weld HAZ [17,18]

BM 509 2377 ͲϳϮ 4.0912 3.6967 2.6529 2.3889 CPAGM 626 2402 ͲϰϮ 3.6505 3.4711 2.7264 2.5231 FPAGM 559 2641 Ͳϳϴ 4.1009 3.7145 2.8367 2.5791 ICR-1 448 2322 Ͳϴϴ 4.1763 3.6509 2.6208 2.3864 ICR-2 475 2369 Ͳϴϵ 4.0565 3.5571 2.5069 2.1834

*Notes: ‘I’ stands for the irradiated material; Values in braces (square brackets) are source references; The underlined and bold values are invalid.

(9)

Table 2. TQcfs estimates for the Table 1 steels compared with other TQ estimates* Steel T0 (°C) (ASTM E1921) TD (0C) TQ-BT (0C) TQ-IGC (0C) TQcfs1 (0C) TQcfs2 (0C) TQcfs3 (0C) TQcfs4 (0C) TQcfs (0C) AISI 403SS -28 -- -- 5.8 Ͳϰϲ ͲϮϰ Ͳϯϵ ϳϯ ͲϮϰ HSST-SAW-51B -- -69 -63 -70 Ͳϳϵ Ͳϳϳ Ͳϴϴ ͲϵϬ Ͳϳϳ HSST-SAW-51B (I)a -- 0 40 36 ϭϭ ϭϳ Ϯϭ ϵ Ϯϭ 22 NiMoCr 3-7 -76 to -86 -- -- -39.5 Ͳϴϱ Ͳϴϱ Ͳϴϱ Ͳϵϲ Ͳϴϱ A302B (ASTM) -- -35 -12.5 -36 ͲͲ ͲͲ Ͳϯϱ Ͳϯϯ Ͳϯϯ BR3

Plate-A302B-New (Ni modified A302B)

-28

-55 -43 -32 Ͳϱϰ Ͳϴϳ Ͳϰϳ Ͳϰϵ Ͳϰϳ BR3

Plate-A302B-New-I (Ni modified A302B) -- 52 118 125 ϳϱ ϭϮϮ ϴϬ ϴϲ ϭϮϮ A212B -- -52.5 -39 -31 ͲͲ ͲͲ ͲϮϴ Ͳϱϰ ͲϮϴ A212B-I -- 2.5 44 61 ͲͲ ͲͲ ϱϵ ϱϴ ϱϵ 01Ti-1 -- -79.4 -79.1 -74 ͲϭϬϬ Ͳϵϵ Ͳϵϰ ͲϭϬϱ Ͳϵϰ 05Ti-1 -- -14.8 17.8 -45 Ͳϲϵ Ͳϳϴ Ͳϱϱ Ͳϱϲ Ͳϱϱ JRQ-UI -43 -72 -68 -46 Ͳϲϰ Ͳϱϲ Ͳϳϲ Ͳϲϲ Ͳϱϲ JRQ-I 67 -16 16 62 ϭϬ ϯϵ ͲϮϳ Ͳϭϯ ϯϵ EUROFER-97 -115 -110 -125 -98 ͲϭϬϳ ͲϭϮϬ ͲϭϬϳ ͲϭϭϮ ͲϭϬϳ EUROFER-97-I -14 -29 -3.5 -62 or 7.5 Ͳϭϯ ϰ͘Ϯ ͲϮϳ ͲϮϯ ϰ͘Ϯ 18MND5 -119 -115 -133 -72 ͲϭϬϬ ͲϭϬϳ ͲϭϬϬ Ͳϭϭϭ ͲϭϬϬ

9Cr-1Mo Steel Simulated Weld HAZ

BM -- -109 -124 -81 ͲϭϬϴ Ͳϭϭϱ ͲϭϭϬ Ͳϭϭϱ ͲϭϬϴ CPAGM -- -92.4 -99 -56 Ͳϴϲ Ͳϳϴ Ͳϴϲ ͲϵϬ Ͳϳϴ FPAGM -- -134 -160 -86 Ͳϭϭϰ Ͳϭϭϳ Ͳϭϭϰ ͲϭϮϱ Ͳϭϭϰ ICR-1 -- -124 -146 -92 ͲϭϮϰ Ͳϭϯϱ ͲϭϮϴ ͲϭϯϬ ͲϭϮϰ ICR-2 -- -112 -128 -92 ͲϭϮϭ Ͳϭϯϴ ͲϭϮϲ Ͳϭϯϵ ͲϭϮϭ

References

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