Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel
Представлены результаты исследования материалов бандажного сварного шва и кольца
 основного металла сосуда давления первого блока реактора типа ВВЭР-440/230. Исследовали
 круглые вырезки материала (трепаны) после радиационного облучения с последующим отжигом и повторным облучением....
Збережено в:
| Опубліковано в: : | Проблемы прочности |
|---|---|
| Дата: | 2010 |
| Автори: | , , |
| Формат: | Стаття |
| Мова: | Англійська |
| Опубліковано: |
Інститут проблем міцності ім. Г.С. Писаренко НАН України
2010
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| Теми: | |
| Онлайн доступ: | https://nasplib.isofts.kiev.ua/handle/123456789/111649 |
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| Назва журналу: | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| Цитувати: | Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel / J. Schuhknecht, U. Rindelhardt, H.W. Viehrig // Проблемы прочности. — 2010. — № 1. — С. 95-104. — Бібліогр.: 9 назв. — англ. |
Репозитарії
Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1860039470902935552 |
|---|---|
| author | Schuhknecht, J. Rindelhardt, U. Viehrig, H.W. |
| author_facet | Schuhknecht, J. Rindelhardt, U. Viehrig, H.W. |
| citation_txt | Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel / J. Schuhknecht, U. Rindelhardt, H.W. Viehrig // Проблемы прочности. — 2010. — № 1. — С. 95-104. — Бібліогр.: 9 назв. — англ. |
| collection | DSpace DC |
| container_title | Проблемы прочности |
| description | Представлены результаты исследования материалов бандажного сварного шва и кольца
основного металла сосуда давления первого блока реактора типа ВВЭР-440/230. Исследовали
круглые вырезки материала (трепаны) после радиационного облучения с последующим отжигом и повторным облучением. Основная задача рабочей программы исследований состояла в
получении распределения механических характеристик реакторных сталей по толщине стенки реактора. Согласно стандарту ASTM E192 определялась базисная температура T₀ с
целью оценки распределения вязкости разрушения по толщине стенки реактора.
Представлено результати дослідження матеріалів бандажного зварного шва
та кільця основного металу посудини тиску першого блоку реактора типу
ВВЕР-440/230. Досліджували круглі вирізки матеріалу (тріпани) після радіаційного опромінення з наступним відпалом і повторним опроміненням.
Основна задача робочої програми досліджень – отримання розподілу механічних характеристик реакторних сталей по товщині стінки реактора. Згідно
зі стандартом ASTM E192 визначали базисну температуру T₀ з метою оцінки
розподілу в’язкості руйнування по товщині стінки реактора.
|
| first_indexed | 2025-12-07T16:54:57Z |
| format | Article |
| fulltext |
UDC 539.4
Study of the Beltline Weld and Base Metal of WWER-440 First
Generation Reactor Pressure Vessel
J. Schuhknecht, U. Rindelhardt, and H.-W. Viehrig
Forschungszentrum Dresden-Rossendorf (FZD), Dresden, Germany
ÓÄÊ 539.4
Èññëåäîâàíèå ìàòåðèàëîâ áàíäàæíîãî ñâàðíîãî øâà è îñíîâíîãî
ìåòàëëà ðåàêòîðà ïåðâîãî ïîêîëåíèÿ ÂÂÝÐ-440
ß. Øóêíåõò, Ó. Ðèíäåëüõàðäò, Ã.-Â. Ôèåðèã
Èññëåäîâàòåëüñêèé öåíòð Äðåçäåí-Ðîññåíäîðô, Äðåçäåí, Ãåðìàíèÿ
Ïðåäñòàâëåíû ðåçóëüòàòû èññëåäîâàíèÿ ìàòåðèàëîâ áàíäàæíîãî ñâàðíîãî øâà è êîëüöà
îñíîâíîãî ìåòàëëà ñîñóäà äàâëåíèÿ ïåðâîãî áëîêà ðåàêòîðà òèïà ÂÂÝÐ-440/230. Èññëåäîâàëè
êðóãëûå âûðåçêè ìàòåðèàëà (òðåïàíû) ïîñëå ðàäèàöèîííîãî îáëó÷åíèÿ ñ ïîñëåäóþùèì îòæè-
ãîì è ïîâòîðíûì îáëó÷åíèåì. Îñíîâíàÿ çàäà÷à ðàáî÷åé ïðîãðàììû èññëåäîâàíèé ñîñòîÿëà â
ïîëó÷åíèè ðàñïðåäåëåíèÿ ìåõàíè÷åñêèõ õàðàêòåðèñòèê ðåàêòîðíûõ ñòàëåé ïî òîëùèíå ñòåí-
êè ðåàêòîðà. Ñîãëàñíî ñòàíäàðòó ASTM E192 îïðåäåëÿëàñü áàçèñíàÿ òåìïåðàòóðà T0 ñ
öåëüþ îöåíêè ðàñïðåäåëåíèÿ âÿçêîñòè ðàçðóøåíèÿ ïî òîëùèíå ñòåíêè ðåàêòîðà.
Êëþ÷åâûå ñëîâà: ðåàêòîðû òèïà ÂÂÝÐ, ðåàêòîðíûå ñòàëè, ìåòàëë ñâàðíîãî
øâà, îñíîâíîé ìåòàëë, òðåïàí, ñâàðíîé øîâ, âÿçêîñòü ðàçðóøåíèÿ, ìåòîä
Master Curve, îáðàçåö òèïà Øàðïè ñ V-îáðàçíûì íàäðåçîì.
Introduction. Nuclear plant operators must guarantee that the structural
integrity of nuclear reactor pressure vessels (RPV) is assured during routine
operations or under postulated accident conditions. The ageing of the RPV steels is
monitored with surveillance program results or predicted by trend curves.
However, embrittlement forecast via trend curves and surveillance specimens may
not reflect the reality. Accordingly, the most realistic evaluation of the fracture
toughness response of RPV material to irradiation is performed directly on RPV
wall samples from decommissioned NPPs. Such a unique opportunity is now
offered with material from the decommissioned Greifswald NPP (WWER-440/230).
The four Greifswald NPP units representing the first generation of WWER-440
reactors were shutdown in 1990 after 11–17 years of operation [1]. Table 1 presents
the operation characteristics of the Units 1 to 4 and the expected neutron fluences.
RPVs in three different conditions are available:
(i) Unit 1 is irradiated, annealed, and reirradiated (IAI);
(ii) Units 2 and 3 are irradiated and annealed (IA);
(iii) Unit 4 is irradiated.
The well-documented different irradiation/annealing states of the four
decommissioned Greifswald RPVs [2] ensure validation of the material properties
under long-term low flux irradiation during industrial recovery annealing and
© J. SCHUHKNECHT, U. RINDELHARDT, H.-W. VIEHRIG, 2010
ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1 95
during subsequent reirradiation. Trepans were extracted from the Units 1, 2, and 4.
We present results of the circumferential core weld SN0.1.4 and the base metal ring
0.3.1 of the RPV from the Unit 1 of the Greifswald WWER-440/230.
Material and Specimens. The critical temperature of brittleness from the
circumferential beltline welding seam SN0.1.4 of Greifswald Unit 1 RPV was
estimated for the initial condition, TK 0 , at 46�C, and after 13 campaigns of
operation at 186�C (TK) [2]. In this state, the RPV was subjected to heat treatment
at 475�C for 152 hours, in order to anneal the irradiation embrittlement in 1988.
The RPV was heat-treated within a region of 0.7 m above and below the
circumferential beltline welding seam No. SN0.1.4. After the annealing, compact
specimens were taken from the weld metal at the inner vessel wall. Sub-size
Charpy specimens were machined and tested. For these specimens the critical
temperature of brittleness, TK, of 30�C was estimated [2]. After the annealing the
operation of Unit 1 was continued for two more years (Table 1). Unit 1 was
shutdown in 1990. Trepans were extracted from the decommissioned Unit 1 RPV
in 2005. The custom-built trepanning device and the trepanning procedure are
described elsewhere [3].
Figure 1 shows the location of the trepans taken from the RPV of Greifswald
Unit 1, from the circumferential beltline welding seam SN0.1.4 and the base metal
ring 0.3.1. At first, the trepans from Unit 1 representing the IAI condition of the
beltline welding seam were investigated. The WWER-440 RPV welding seams are
X-butt multilayer submerged welds. They consist of a welding root welded with an
unalloyed wire Sv-08A and the filling material welded with the alloyed wire
Sv-10KhMFT. The chemical compositions measured at 3 locations of the welding
seam belong to the alloyed filling material and generally agree with the information
in the manufacturing protocol [2]. Cu and P contents are within the range specified
in the manufacturing guidelines of the WWER-440/230, but both are clearly higher
than in the specification of the next generation (model 213) with maximum allowed
P and Cu contents of 0.01 and 0.1%, respectively [5].
J. Schuhknecht, U. Rindelhardt, and H.-W. Viehrig
96 ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1
T a b l e 1
Operation Characteristics and Expected Maximum Neutron Fluences
of Greifswald Units 1 to 4
Unit Operation period Effective
days
Annealed
in
Azimuthal maximum of N E�0 5. MeV
in units of 1019 n/cm2
date cycles inner wall
axial
maximum
inner wall
weld 4
outer wall
axial
maximum
outer wall
weld 4
1 1974–1988 13 4205.0 1988 5.53 3.93 1.40 0.96
1* 1988–1990 2 627.4 – 0.16 0.10 0.05 0.03
2 1975–1990 14 4067.4 1990 6.68 4.70 1.70 1.16
3 1978–1990 12 3581.8 1990 4.40 3.40 0.68 0.50
4 1979–1990 11 3207.9 not 4.00 3.10 0.62 0.45
* Reirradiated.
Trepans 1-1 and 1-4 were cut into discs each of 10 mm thickness using a wire
travelling electro-erosion discharging machine (EDM). The location of the welding
seam within trepan 1-1 was metallographically examined and depicted in Fig. 2
together with the cutting scheme of the disc 1-1.1. The welding root is located
within a distance of about 60 to 80 mm relative to the inner RPV wall. The Charpy
size SE(B) specimens were precracked (a W �0 5. ) and 20% side-grooved. As
shown in Fig. 3, the orientation of the SE(B) specimen of the weld metal is TS
(specimen axis and crack growth direction across the vessel wall) and for the base
metal/trepan 1-4) is LS according to ASTM E399 [6]. The crack orientation is in
correspondence with the surveillance specimens in Russian WWER-440/213
reactors.
Study of the Beltline Weld and Base Metal ...
ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1 97
Fig. 1. RPV WWER 440 Greifswald Unit 1 and locations of the sampled trepans.
Fig. 2. Metallographic section of the welding seam trepan 1-1.
Testing and Evaluation. SE(B) specimens representing 11 thickness locations
of trepan 1-1 and 5 thickness locations from base metal trepan 1-4 were tested and
evaluated according to ASTM E1921-05/08 [7]. The precracked and side- grooved
Charpy size SE(B) specimens were monotonously loaded until they failed by
cleavage instability. Standard Master Curve (MC) reference temperatures T0 were
evaluated with the measured J-integral-based cleavage fracture toughness values,
K Jc , applying the multitemperature procedure of ASTM E1921-05/08 [7]. In
addition, the modified MC analysis of the SINTAP-procedure [8] was used for the
evaluation of the measured K Jc-values. The SINTAP lower tail analysis contains
three steps, and guides the user towards the most appropriate estimate of the
reference temperature, T SINTAP
0 , describing the samples having the lower
toughness.
Instrumented Charpy V-notch impact tests on reconstituted specimens were
performed according to DIN EN 10045-1 and EN ISO 14556. The impact energy,
lateral expansion and fracture appearance temperature curves were fitted by the
tanh approach. Such Charpy-V parameters as transition temperatures and the upper
shelf energy were evaluated on specimens from different thickness locations.
Samples for metallographic investigations and hardness tests were prepared
from selected tested specimens, in order to assess the structure in the vicinity of the
fatigue crack tip.
Results and Discussion. Figure 4 illustrates the reference temperature T0
evaluated according to ASTM E1921-05/08 and the Charpy-V transition temperature
of the investigated discs of trepan 1-1. The background shows the design of the
welding seam. Through the wall thickness, T0 shows a wavelike behavior. After
an initial increase of T0 from 10�C at the inner surface to 50�C at 22 mm distance
from it, T0 decreases to 41�C at a distance of 70 mm, finally increasing to the
maximum 67�C towards the outer RPV wall. The lowest T0 value was measured
in the root region of the welding seam representing a uniform fine-grain ferritic
structure. Beyond the welding root T0 shows a wavelike behavior with a span of
about 50 K. Additionally, the MC SINTAP procedure was applied to determine
98 ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1
Fig. 3. Cutting scheme of disc 1-1.1.
J. Schuhknecht, U. Rindelhardt, and H.-W. Viehrig
T SINTAP
0 representing the brittle fraction of the data set. For some thickness
locations there are remarkable differences between T0 and T SINTAP
0 values.
This strongly indicates that the material is not fully homogeneous, which is
not unusual for the investigated multilayer weld metal. Figure 5 shows the K Jc
values versus the test temperature normalized to T0 of the individual thickness
location. The K Jc values generally follow the course of the MC, though the scatter
is large. Nevertheless, only 2 out of about 100 values of K Jc lie below the 2%
fracture probability line. As mentioned above, the beltline welding seam of
Greifswald Unit 1 was recovery-annealed and reirradiated to low fluences.
Taking into account that after 13 campaigns’ operation TK � �186 C, the
results presented here and those determined on subsize impact specimens [2] show
that the embrittlement was almost fully undone due to the recovery-annealing. The
re-embrittlement during 2 campaigns’ operation can be assumed to be low. Hence,
variation of T0 measured through the thickness of the multilayer welding seam
SN0.1.4 results basically from differences in the structure of the welding beads.
ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1 99
Fig. 4. Course of the reference temperatures T0 through the welding seam SN0.1.4 of Greifswald
Unit 1.
Distance from the RPV inner wall (mm)
T
em
pe
ra
tu
re
( �
C
)
Fig. 5. KJc values of trepan 1-1 versus test temperature normalized to T0 of the individual thickness
location.
KJc ( ) ,1T MPa m
T T� �0 , C
Study of the Beltline Weld and Base Metal ...
Figures 6 and 7 depict the structure in the vicinity of the crack tip of TS-oriented
SE(B) specimens in different thickness locations. Generally, TS-oriented specimens
have a uniform structure along the fatigue crack front (plane LS), thus crack tip is
located in a varying uniform of the welding beads. Figure 6 shows the specimen
structure from the thickness location 22 mm. The crack tip is located in a coarse-
grain bainitic structure whose grains are framed with proeutectoid ferrite. This
coarse-grain structure yields a T0 of 49.1�C. For comparison, Fig. 7 shows the
structure in the region of the welding root in a thickness location of 70 mm, where
T0 40 6� �. C was determined. There, the crack tip is located directly in a fine-grain
structure of high ferrite content which was welded with the unalloyed wire Sv-08A.
This example demonstrates the effect of the specimen orientation on a
multilayer welding seam. Unlike TS specimens, the structure of TL specimens
varies along the fatigue crack front (plane LS), which is featured in the welding
root region depicted in Fig. 7. It means that TS and TL specimens have a
differentiating and integrating behavior, respectively. Therefore TS specimens are
more sensitive to variations in the structure of the multilayer weld metal. The wide
range of T0 values spanning about 50 K can be explained by the location of the
crack tip in the different structures of the welding beads.
According to the Russian regulatory guide PNAÉ-G-7-002-086 [9] the
surveillance specimens of weld metal of WWER-440 (213) RPV origin from
thickness locations beyond the welding root. The K Jc values of the Sv-10KhMFT
filling layers (distance of 84–118 mm from the inner surface) are evaluated
separately. According to ASTM E1921-05 [7], T0 of the overall evaluation is
100 ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1
Fig. 6. Metallography of the filling (layer 22 mm).
Fig. 7. Metallography of the root (70 mm).
J. Schuhknecht, U. Rindelhardt, and H.-W. Viehrig
20 9. �C (Fig. 8) and the T SINTAP
0 evaluated with SINTAP of the more conservative
step 3 is 22.3�C. As shown in Fig. 8, the majority of the K Jc values from thickness
location of 94 mm (disc 1-1.12) are below the MC for 2% fracture probability.
The T0 value of that layer is clearly higher, as compared to the neighboring
discs (Fig. 4). Hence, there are brittle zones within the welding seam. Due to the
differentiating character of the precracked TS specimen, very small brittle zones
can be detected. This implication is confirmed by the metallographic section shown
in Fig. 9, where the crack tip is located directly in a fusion zone between two
welding beads. One can state that surveillance test series whose specimens
originate from different thickness location of the filling layers can lead to a T0 that
represents the brittle constituent. As illustrated in Fig. 8, the 2% MC indexed with
T SINTAP
0 (step 3) representing the brittle constituent of the dataset envelops the K Jc
values except the one that is located directly on the line. As shown in Fig. 4, at the
location near the inner RPV wall the evaluated TT41 51J C� � and thus is close to
the reported TK 0 46� �C [2].
The level of evaluated upper shelf energy coincides with that expected for
WWER-440 weld metals. As mentioned before, TK � �30 C was estimated for
sub-size impact specimens (type KLST according to DIN EN 10045-1). This TK
is based on a correlation between the TT1 9. J transition temperature determined
ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1 101
Fig. 8. KJc values from the thickness locations beyond the welding root versus the test temperature.
KJc ( ) ,1T MPa m
T , �C
Fig. 9. Metallographic sections of the SE(B) specimen from the thickness location 94 mm.
Study of the Beltline Weld and Base Metal ...
with KLST specimens and the TT41J transition temperature of standard Charpy-V
specimens. The scatter of this correlation of � �35 C is rather high, as well as
uncertainty of the applied conversion. Taking into account the difference in the
orientation of the specimens and the reirradiation of two cycles, the TT41J
estimated with KLST specimens after the recovery-annealing is quite realistic. In
this case, the reirradiation causes an increase of TT41J by 21�C. The TT41J
transition temperatures of the other thickness locations are lower.
A direct correlation between T0 and TT41J of the investigated weld metal is
questionable due to the different thickness locations (S) of the crack tip and notch
root in precracked SE(B) and the reconstituted Charpy-V specimens, respectively.
Moreover, the notch root of the reconstituted Charpy-V specimens has a different
axial position (T). Hence, the structures at the crack tip and notch root are different.
This becomes apparent for the thickness layer of 92 mm (disc 1-1.12) where T0
agrees with TT41J . Normally, T0 is expected to be about 40�C lower than TT41J .
Based on the results presented here, a low re-embrittlement can be stated for
thickness locations close to the inner RPV wall. This is more obvious for the
Charpy-V results. The fracture-toughness-based T0 shows a higher inherent scatter,
which is caused by the differentiating character of precracked TS specimens.
Figure 10 depicts the measured reference temperature T0 from 5 thickness
locations, tested and evaluated according to ASTM E1921-05/08, of the base metal
102 ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1
Fig. 10. Course of T0 and neutron fluence through the RPV wall trepan 1-4 of Greifswald Unit 1.
Fig. 11. KJc values of trepan 1-4 versus the test temperature normalised to T0 of the individual discs.
Distance from the RPV inner wall (mm)
T
em
pe
ra
tu
re
( �
C
)
N
eu
tr
on
fl
ue
nc
e
in
10
19
n/
cm
2
( E
�
0
5.
M
eV
)
T T� �0 , C
KJc ( ) ,1T MPa m
J. Schuhknecht, U. Rindelhardt, and H.-W. Viehrig
trepan 1-4. The course of the reference temperature T0 through the RPV wall
shows a regular behavior. T0 varies little over the wall thickness and is under
� �100 C. The effect of post-annealing reirradiation can be assumed to be low for the
base metal of the RPV wall. Figure 11 shows the K Jc values adjusted to the
specimen thickness of 1T versus the test temperature normalized to individual T0
of five thickness locations. The K Jc values generally follow the course of the MC
but the scatter here is also large. More than 2% of the values lie outside the fracture
toughness range for 2 and 98% fracture probabilities. A possible cause can be the
structure of the base metal. Metallographic investigations will be performed to find
an explanation for the scatter.
Conclusions. We present first results of the investigations performed with
reactor pressure vessel material of the Russian WWER-440 type reactors.
1. Trepans were taken from the beltline weld and the base metal of the Unit 1
RPV. This RPV was annealed after 15 years of operation and operated for two
more years. At first, the trepan of the beltline welding seam was investigated by
Master Curve and Charpy V-notch testing. Specimens with TS orientation from 11
locations through the thickness of the welding seam were tested. The differences in
T0 through the beltline welding seam are not the result of the low reirradiation, but
are caused by the nonhomogenous structure of the multilayer welding seam. Due to
the differentiating character of the precracked TS specimen, very small brittle
zones can be detected.
2. With the application of the MC modification in the SINTAP procedure a
reference temperature T SINTAP
0 can be evaluated which is based on the brittle
constituent of a dataset. There are remarkable differences between T0 and T SINTAP
0
indicating macroscopic inhomogeneous weld metal for some thickness locations.
Specimens with LS orientation from 5 locations through the thickness of the RPV
from the base metal trepan 1-4 were tested and evaluated with the Master Curve.
The course of the reference temperature T0 in the base metal shows a regular
behavior over the RPV wall thickness. T0 varies little over the wall thickness and
is under � �100 C. There is remarkable scatter in the K Jc values and more K Jc
values than expected lie below the 2% fractile which indicates macroscopic
inhomogeneity.
3. The effect of post-annealing reirradiation in the base metal of the RPV
wall can be assumed to be low for the investigated base metal, as well as for the
weld metal. The orientations for base and weld metal show that the crack front is
located in a uniform structure, but nevertheless the scatter of the K Jc values is
high.
4. The crack tip position in the multilayer welding seam is crucial. A
comparison regarding the orientation of SE(B) specimens with the Master Curve
will follow. Generally, the effect of the recovery annealing was confirmed with the
fracture toughness and Charpy-V testing. The TT41J estimated with subsize KLST
impact specimens after the annealing was confirmed by the testing of standard
Charpy V-notch specimens.
Acknowledgment. This study was funded by the German Federal Ministry of
Economics and Technology (Reactor Safety Research Project Grant No. 1501331).
ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1 103
Study of the Beltline Weld and Base Metal ...
Ð å ç þ ì å
Ïðåäñòàâëåíî ðåçóëüòàòè äîñë³äæåííÿ ìàòåð³àë³â áàíäàæíîãî çâàðíîãî øâà
òà ê³ëüöÿ îñíîâíîãî ìåòàëó ïîñóäèíè òèñêó ïåðøîãî áëîêó ðåàêòîðà òèïó
ÂÂÅÐ-440/230. Äîñë³äæóâàëè êðóãë³ âèð³çêè ìàòåð³àëó (òð³ïàíè) ï³ñëÿ ðà-
ä³àö³éíîãî îïðîì³íåííÿ ç íàñòóïíèì â³äïàëîì ³ ïîâòîðíèì îïðîì³íåííÿì.
Îñíîâíà çàäà÷à ðîáî÷î¿ ïðîãðàìè äîñë³äæåíü – îòðèìàííÿ ðîçïîä³ëó ìåõà-
í³÷íèõ õàðàêòåðèñòèê ðåàêòîðíèõ ñòàëåé ïî òîâùèí³ ñò³íêè ðåàêòîðà. Çã³äíî
ç³ ñòàíäàðòîì ASTM E192 âèçíà÷àëè áàçèñíó òåìïåðàòóðó T0 ç ìåòîþ îö³íêè
ðîçïîä³ëó â’ÿçêîñò³ ðóéíóâàííÿ ïî òîâùèí³ ñò³íêè ðåàêòîðà.
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investigations of the former Greifswald NPP: Fluence calculations and Nb
based fluence measurements,” in: Proc. ICONE14/FEDSM2006, Contribution
ICONE 14-89578 (2006).
2. R. Ahlstrand, E. N. Klausnitzer, D. Langer, et al., “Evaluation of the recovery
annealing of the reactor pressure vessel of NPP Nord (Greifswald) Units 1 and
2 by means of subsize impact specimens,” in: E. Lendell (Ed.), Radiation
Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International
Review (Fourth Volume), ASTM STP 1170, Philadelphia (1993), pp. 321–
343.
3. H.-W. Viehrig, U. Rindelhardt, and J. Schuhknecht, “Post mortem
investigations of the NPP Greifswald WWER-440 reactor pressure vessels,”
in: Proc. of 19th Int. Conf. on Structural Mechanics in Reactor Technology
(SMiRT19, 12–17 August, Toronto) (2007).
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Received 21. 06. 2009
104 ISSN 0556-171X. Ïðîáëåìû ïðî÷íîñòè, 2010, ¹ 1
J. Schuhknecht, U. Rindelhardt, and H.-W. Viehrig
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| id | nasplib_isofts_kiev_ua-123456789-111649 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 0556-171X |
| language | English |
| last_indexed | 2025-12-07T16:54:57Z |
| publishDate | 2010 |
| publisher | Інститут проблем міцності ім. Г.С. Писаренко НАН України |
| record_format | dspace |
| spelling | Schuhknecht, J. Rindelhardt, U. Viehrig, H.W. 2017-01-13T15:12:02Z 2017-01-13T15:12:02Z 2010 Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel / J. Schuhknecht, U. Rindelhardt, H.W. Viehrig // Проблемы прочности. — 2010. — № 1. — С. 95-104. — Бібліогр.: 9 назв. — англ. 0556-171X https://nasplib.isofts.kiev.ua/handle/123456789/111649 539.4 Представлены результаты исследования материалов бандажного сварного шва и кольца
 основного металла сосуда давления первого блока реактора типа ВВЭР-440/230. Исследовали
 круглые вырезки материала (трепаны) после радиационного облучения с последующим отжигом и повторным облучением. Основная задача рабочей программы исследований состояла в
 получении распределения механических характеристик реакторных сталей по толщине стенки реактора. Согласно стандарту ASTM E192 определялась базисная температура T₀ с
 целью оценки распределения вязкости разрушения по толщине стенки реактора. Представлено результати дослідження матеріалів бандажного зварного шва
 та кільця основного металу посудини тиску першого блоку реактора типу
 ВВЕР-440/230. Досліджували круглі вирізки матеріалу (тріпани) після радіаційного опромінення з наступним відпалом і повторним опроміненням.
 Основна задача робочої програми досліджень – отримання розподілу механічних характеристик реакторних сталей по товщині стінки реактора. Згідно
 зі стандартом ASTM E192 визначали базисну температуру T₀ з метою оцінки
 розподілу в’язкості руйнування по товщині стінки реактора. This study was funded by the German Federal Ministry of
 Economics and Technology (Reactor Safety Research Project Grant No. 1501331) en Інститут проблем міцності ім. Г.С. Писаренко НАН України Проблемы прочности Научно-технический раздел Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel Исследование материалов бандажного сварного шва и основного металла реактора первого поколения ВВЭР-440 Article published earlier |
| spellingShingle | Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel Schuhknecht, J. Rindelhardt, U. Viehrig, H.W. Научно-технический раздел |
| title | Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel |
| title_alt | Исследование материалов бандажного сварного шва и основного металла реактора первого поколения ВВЭР-440 |
| title_full | Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel |
| title_fullStr | Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel |
| title_full_unstemmed | Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel |
| title_short | Study of the Beltline Weld and Base Metal of WWER-440 First Generation Reactor Pressure Vessel |
| title_sort | study of the beltline weld and base metal of wwer-440 first generation reactor pressure vessel |
| topic | Научно-технический раздел |
| topic_facet | Научно-технический раздел |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/111649 |
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