Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant
The quality and safety of operation of the main circulating pipeline of the nuclear power plant is being studied in order to extend the life of the pipelines of the reactor unit of the NPP on the basis of the development of a scientifically sound mathematical model and algorithm for their technical...
Saved in:
| Published in: | Вопросы атомной науки и техники |
|---|---|
| Date: | 2019 |
| Main Authors: | , , , |
| Format: | Article |
| Language: | English |
| Published: |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2019
|
| Subjects: | |
| Online Access: | https://nasplib.isofts.kiev.ua/handle/123456789/194949 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| Journal Title: | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| Cite this: | Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant / H. Hrinchenko, R. Trisch, V. Burdeina, S. Chelysheva // Problems of atomic science and technology. — 2019. — № 2. — С. 104-110. — Бібліогр.: 7 назв. — англ. |
Institution
Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1859977291567726592 |
|---|---|
| author | Hrinchenko, H. Trisch, R. Burdeina, V. Chelysheva, S. |
| author_facet | Hrinchenko, H. Trisch, R. Burdeina, V. Chelysheva, S. |
| citation_txt | Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant / H. Hrinchenko, R. Trisch, V. Burdeina, S. Chelysheva // Problems of atomic science and technology. — 2019. — № 2. — С. 104-110. — Бібліогр.: 7 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | The quality and safety of operation of the main circulating pipeline of the nuclear power plant is being studied in order to extend the life of the pipelines of the reactor unit of the NPP on the basis of the development of a scientifically sound mathematical model and algorithm for their technical diagnostics. The complex estimation of the quality of operation of pipeline systems is proposed, taking into account the peculiarities of their stress-strain state and seismic stability. The purpose of the article is to substantiate the integrated assessment of the quality and safety of operation of pipelines of the reactor unit of the NPP on the basis of the development of a scientifically sound mathematical model and algorithm for their technical diagnostics in order to extend the life of the operation. Research methods: calculations by mathematical model, comparison of results of calculation, forecasting of boundary parameters of technical condition and monitoring of mechanical properties of main pipeline material, inspection, qualification, determination of residual resource of buildings, structures, foundations and metal structures taking into account geotechnical and seismotectonic conditions. It is determined that in the initial period of existence of the projected residual resource seismic activity in the zone 300...500 km from the location of the NPP is less safe than seismic activity, which takes place in the final period of the projected residual resource, as a sharp increase in the level of damage from seismic activity leads to exceeding the limit of permissible the level of damage to the material of the main pipeline.
Досліджуються якість та безпека експлуатації головного циркуляційного трубопроводу атомної електростанції з метою подовження ресурсу трубопроводів реакторного відділення АЕС на основі розробки науково обґрунтованої математичної моделі та алгоритму їх технічної діагностики. Запропоновано комплексну оцінку якості експлуатації трубопровідних систем шляхом врахування особливостей їх напружено-деформованого стану та сейсмостійкості. Метою статті є обґрунтування комплексної оцінки якості та безпеки експлуатації трубопроводів реакторного відділення АЕС на основі розробки науково обґрунтованої математичної моделі та алгоритму їх технічної діагностики з метою продовження терміну експлуатації. Методи дослідження: розрахунки за допомогою математичної моделі; порівняння результатів обчислення, прогнозування граничних параметрів технічного стану та моніторинг механічних властивостей матеріалу магістрального трубопроводу; обстеження, кваліфікація, визначення залишкового ресурсу будівель, споруд, фундаментів і металоконструкцій з урахуванням геотехнічних і сейсмотектонічних умов. Визначено, що в начальний період існування прогнозованого залишкового ресурсу сейсмічна активність у зоні 300…500 км від розташування АЕС є менш безпечніша, ніж сейсмічна активність, яка проходить у завершальний період прогнозованого залишкового ресурсу, так як різке підвищення рівня пошкодження від сейсмічної активності призводить до перевищення межі допустимого рівня пошкодження матеріалу магістрального трубопроводу.
Исследуются качество и безопасность эксплуатации главного циркуляционного трубопровода атомной электростанции с целью продления ресурса трубопроводов реакторного отделения АЭС на основе разработки научно обоснованной математической модели и алгоритма их технической диагностики. Предложена комплексная оценка качества эксплуатации трубопроводных систем путем учета особенностей их напряженно-деформированного состояния и сейсмостойкости. Целью статьи является обоснование комплексной оценки качества и безопасности эксплуатации трубопроводов реакторного отделения АЭС на основе разработки научно обоснованной математической модели и алгоритма их технической диагностики с целью продления срока эксплуатации. Методы исследования: расчеты с помощью математической модели; сравнение результатов вычисления, прогнозирования предельных параметров технического состояния и мониторинг механических свойств материала магистрального трубопровода; обследование, квалификация, определение остаточного ресурса зданий, сооружений, фундаментов и металлоконструкций с учетом геотехнических и сейсмотектонических условий. Определено, что в начальный период существования прогнозируемого остаточного ресурса сейсмическая активность в зоне 300...500 км от расположения АЭС менее безопасная, чем сейсмическая активность, которая проходит в заключительный период прогнозируемого остаточного ресурса, так как резкое повышение уровня повреждения от сейсмической активности приводит к превышению предела допустимого уровня повреждения материала магистрального трубопровода.
|
| first_indexed | 2025-12-07T16:24:12Z |
| format | Article |
| fulltext |
ISSN 1562-6016. PASТ. 2019. №2(120), p. 104-110.
UDC 621.311:621.313
ALGORITHM OF TECHNICAL DIAGNOSTICS OF THE
COMPLICATED DAMAGE TO THE CONTINUED RESOURCE OF THE
CIRCULATION PIPELINE OF THE NUCLEAR POWER PLANT
H. Hrinchenko
1
, R. Trisch
2
, V. Burdeina
3
, S. Chelysheva
4
Ukrainian Engineering-Pedagogical Academy, Kharkov, Ukraine
Е-mail:
1
a.kiporenko@ukr.net;
2
trich_@ukr.net;
3
zamorskavika@ukr.net;
4
сhelysheva.svitlana@gmail.com
The quality and safety of operation of the main circulating pipeline of the nuclear power plant is being studied in
order to extend the life of the pipelines of the reactor unit of the NPP on the basis of the development of a
scientifically sound mathematical model and algorithm for their technical diagnostics. The complex estimation of
the quality of operation of pipeline systems is proposed, taking into account the peculiarities of their stress-strain
state and seismic stability. The purpose of the article is to substantiate the integrated assessment of the quality and
safety of operation of pipelines of the reactor unit of the NPP on the basis of the development of a scientifically
sound mathematical model and algorithm for their technical diagnostics in order to extend the life of the operation.
Research methods: calculations by mathematical model, comparison of results of calculation, forecasting of
boundary parameters of technical condition and monitoring of mechanical properties of main pipeline material,
inspection, qualification, determination of residual resource of buildings, structures, foundations and metal
structures taking into account geotechnical and seismotectonic conditions. It is determined that in the initial period
of existence of the projected residual resource seismic activity in the zone 300...500 km from the location of the
NPP is less safe than seismic activity, which takes place in the final period of the projected residual resource, as a
sharp increase in the level of damage from seismic activity leads to exceeding the limit of permissible the level of
damage to the material of the main pipeline.
INTRODUCTION
The problem of improving the quality, safety and
lifetime of NPP power units is one of the most
important and acute problems not only of nuclear power
engineering but also of the whole fuel and energy
complex of Ukraine. This problem can be solved only in
complex, with joint and parallel solution of the tasks of
extending the resource of individual elements of the
equipment, taking into account their mutual influence
on the reliability and durability of power units. In order
to ensure safety over the project life and the quality of
operation of the power unit, it is necessary to create an
effective mechanism for inspection of the technical state
of the base metal and welded joints of the pipeline,
which would optimize the process of its operation,
based on a favorable balance of economic indicators and
safety. In particular, such a mechanism will enable the
smooth transition to the operation of the power unit,
without its long-term stop and economic losses which
are associated with this, in time out of the project [1].
ANALYSIS OF RECENT RESEARCH
AND PUBLICATIONS
Many of the native and foreign scientists are
engaged in theoretical and experimental issues of
forecasting the resource and assessing the quality of
operation. In the works of native and foreign authors
such as I. Fursov, G. Belkin, Y. Golodnov, S. Lizunov,
V. Strelnikov, P. Svi, S. Polischuk, G. Kanyuk,
M. Girya, R. Hall, J.H. Taylor, J.I. Boccio, on the basis
of research and own experience, is recommended to use
modern methods and methods of control and diagnostics
to assess the technical condition, but the estimates are
considered outside the context of the continuation of the
resource of mechanical equipment. The existing
regulatory framework for the safe operation of NPP,
including design standards (DS) 306.2.099-2004, DS
306.2.106-2005, DS 306.2.141-2008 etc. They contain
the basic criteria and requirements for safety of
equipment of the NPP in the established period of
operation, but does not regulate the conduct of complex
analysis of the quality of equipment, because they do
not take into account changes in technical
characteristics and parameters during its operation,
different degrees of lifetime due to the influence of
operational and regime conditions [2].
SELECTION OF PREVIOUSLY
UNSETTLED PARTS OF THE GENERAL
PROBLEM
Further scientific and mathematical reasoning
requires an assessment of the quality of operation and
technical condition of the equipment, namely: analysis
of technical documentation, expert examination,
analysis of the aging mechanism, refinement of the
boundary states and their criteria, calculation of
stressed-deformed state, calculation of strength, which
will allow the extension of the term service of NPP
power units.
The purpose of the article is to substantiate the
integrated assessment of the quality and safety of
operation of pipelines of the reactor unit of the NPP on
the basis of the development of a scientifically sound
mathematical model and algorithm for their technical
diagnostics in order to extend the life of the operation.
To offer a comprehensive assessment of the quality of
operation of pipeline systems, taking into account the
features of their stress-strain state and seismic
resistance.
mailto:a.kiporenko@ukr.net
mailto:trich_@ukr.net
mailto:zamorskavika@ukr.net
mailto:helysheva.svitlana@gmail.com
In order to achieve this goal, it is necessary to create
an algorithm for a comprehensive assessment of the
quality and safety of operation, in the presence of
accelerated processes of wear of pipelines of the reactor
unit of the NPP based on the following mechanisms of
accumulation of damage:
1) to analyze the statistical data on the reliability and
efficiency of the equipment;
2) to create data bases of groups and equipment
elements, their ranking according to the degree of
criticality;
3) to develop quality criteria and methods for
determining the residual resource;
4) to examine, qualify, determine the residual life of
buildings, structures, foundations and metal structures
taking into account geotechnical and seismotectonic
conditions;
5) to develop methods for optimizing operating
modes of equipment in order to reduce the rate of
damage (resource consumption rate) of critical elements
of equipment;
6) to develop methods of technical diagnostics,
control and monitoring of the technical condition and
equipment remaining equipment.
THE PRESENTATION OF THE MAIN
MATERIAL
The quality and safety of the power unit depends on
the technical condition of all its power systems, both
main and backup. One of the main power unit systems
is piping systems, the technical condition of which is
determined by the quality of all elements, namely the
linear part, the pump equipment and the spare part. The
most important factors determining the technical
condition are: duration of operation, steel stamp of the
pipeline, actual operating regimes, corrosion activity of
the coolant (water, steam), frequency of periodic tests
with high pressure, internal pressure in the pipeline,
temperature and composition of the coolant, weight load
(supports, fasteners), vibration load.
Changing the technical state of the metal pipelines
as a result of deterioration of mechanical properties
arises due to:
the appearance and development of corrosion
defects in the metal pipeline;
nucleation and growth of tidal cracks in places of
concentration of voltage, defects from tidal and low
cyclic loading;
extinction and cracking of metal pipelines as a
result of vibration load.
According to the purpose of the work, the
mechanisms of accumulation of damage are factors that
arise as separate mechanisms of accumulation of
damage, but, as a rule, they are mixed. The presence of
one of the destructive factors leads to the strengthening
of others. Thus, for assessing the technical condition
and forecasting of the resource of piping systems, an
algorithm for a comprehensive assessment of the quality
and safety of operation is proposed, taking into account
a complex of mechanisms of accumulation of damage,
which consists of several stages.
The first stage. It is necessary to construct a three
dimensional (shell) model of the pipeline and define the
control areas of the metal on straight and bent sections.
This makes it possible to determine the stresses arising
from the external and internal sides of the pipeline walls
(Fig. 1).
Fig. 1. Model of the main circulating pipeline
and control circuits for typical pipeline sections
The second stage. Determine the actual load under
different operating conditions: NOC normal operating
conditions; VNOC violation of normal operating
conditions; HT – hydraulic tests. The construction of the
load unit, taking into account the low cycle and
vibration load, allows us to estimate the stress-strain
state of the pipeline and is the starting point for
calculating the actual cyclic loads of Ni over the
lifetime. According to the load diagram, the cyclic
strength of the main circulating pipeline is considered to
be secured if, in the presence of various cyclic loads Ni,
the condition:
1 0
k
i
N
i i
N
a a
N
, (1)
where а is an accumulated fatigue damage to equipment
and pipelines from load operation cycles; [aN] is a
permissible value of accumulated fatigue damage,
[aN]=1; 0[ ]iN is allowable number of load cycles. The
actual number of cycles is determined by constructing a
load block with a note of the operating parameters of the
pressure Рі and the corresponding pressure differences
∆Рі. If there are several modes, then the accumulated
fatal damage to the equipment and pipelines from load
operation cycles is determined by:
[ ]
[ ]
[ ]
, (2)
where [ ] , [ ] , [ ] – the number of
cycles that can withstand the pipeline in load mode NO,
VNO, HT, respectively; [ ] , [ ] , [ ] .
The combination of the main cyclic load with amplitude
(А) frequency f0 and frequency f, which is imposed
with the amplitude <а>, causes a decrease in the
admissible number of basic low frequency load cycles,
which is proposed to take into account the input
coefficient – the coefficient of reduction of durability
in the application of high frequency cycles. The
coefficient is determined by the formula:
,
0
a
а
f
f
(3)
where f0 = 1/(t1+t2) is the frequency of the main cycle of
variable stresses, which is determined without taking
into account the period of time during which there is an
overlay of additional stresses on the constant, hz; t1 is
transition time, hours; t2 is fixed working time, hours;
<а> is amplitude of the given stresses of the vibrational
component of the cycle, MPa (kgf/mm
2
); (а) is
amplitude of the given stresses of the main cycle
without the concentration of stress, MPa (kgf/mm
2
); is
a coefficient depending on the material (normative
parameter is chosen according to Rules and norms in
atomic energy 7-002-86) [3]. The main load cycle of the
damage
*
3a is determined by the formula:
.0
*
3 iiii
NNa (4)
To verify the fulfillment of this condition, it is
necessary to determine how the permissible number of
load cycles 0[ ]iN when mechanical properties change,
and the actual cyclic loads of different types of Ni. The
total (permissible) number of cycles 0[ ]iN to fracture
consists of two terms: Nз is the number of cycles to the
origin of the defect, Nр is the number of cycles at the
stage of development of the defect.
0[ ] .i З РN N N (5)
The number of cycles before the defect is generated
by the Coffin-Manson equation. With the help of this
equation, we establish the relationship between the
amplitude of the deflection deformation, the mechanical
properties of the metal and the number of cycles Nз.
Third stage. To determine the actual mechanical
properties of the metal pipeline and its geometric
dimensions to determine the most dangerous from the
point of view of the integrity of the pipelines, for which
the greatest loads and impacts are possible. The
minimum values of current mechanical properties and
their values of wall thickness were determined by the
results of thickness measurement, and the radii of
curvature were selected according to the executive
diagrams and work drawings. Since there are two load
modes, a rigid (with a constant magnitude of
deformation values) and a soft (with a constant
magnitude of voltage values), then this fact needs to be
taken into account when determining Nз. Also, load
modes are distinguished by symmetry, which is
proposed to be taken into account by means of
determining the coefficient of asymmetry: by stress
min maxR / and deformation
e min max/R e e , that is,
the ratio of the corresponding indicators at minimum
and maximum loads in the cycle. For a rigid symmetric
loading regime, the number of cycles before the defect
is generated is determined from the equation:
1
1
1
ln
1
4( )
,х
З
а
ZN
е
Е
(6)
where ae – the amplitude of the actual deformations at
the top of the defect, MPa (kgf/mm
2
); Z is relative
narrowing, %; 1 is rigid cyclic load index; 1 is
limit of fatigue of a metal with symmetrical loading,
MPa (kgf/mm
2
):
1 0.4 mR ; Е is modulus of
elasticity, MPa (kgf/mm
2
). Indicator
1 is determined
depending on the strength of the metal:
1=0.5 at 700 MPa
m
R ;
1 0.5 0.0002( 700)mR at 700 MPa.
m
R (7)
For a soft symmetric loading regime, the number of
cycles is determined from the equation:
2
1
1
ln
1
4( )
,х
З
а
ZN
е
Е
(8)
where 2 is is the index of soft cyclic loading, which is
determined by the formula:
0.2
2
1.2 0.35
m
R
R
. (9)
In order to determine the number of cycles with
asymmetric load it is proposed to take into account the
asymmetry of the cycle by deformation by determining
an equivalent load:
̃
⁄
, (10)
where ke
is maximum deformation to crack formation
at the top of the defect, MPa (kgf/mm
2
); еа is amplitude
of deformation at the peak of the defect, MPa
(kgf/mm
2
); еav is average deformation at the same point,
MPa (kgf/mm
2
). The values of еа and еср for formula (7)
are determined as follows:
⁄ ; ( ) ⁄ , (11)
where max min,e e – respectively, the smallest and largest
deformation in the process of cyclic change in pressure
(voltage), MPa (kgf/mm
2
). On the basis of the definition
ae and by adding its value, instead of the value of the
amplitude of the actual deformations at the vertex of the
defect (еа), by formulas (5) and (7), we determine the
number of cycles for hard (9) and soft (10) asymmetric
loaded, respectively:
√
(
⁄
)
, (12)
√
⁄
. (13)
The number of cycles at the stage of development of
a defect with cyclic loaded Nр is determined by the
formula:
0
,
( ) e
lc
p n
l e Ie
da
N
c K
(14)
where lC is the critical depth of the defect satisfying the
condition , m; 0.8 ,Ie IeCK K l0 – initial
data of the depth of the defect, m; da is growth rate of
the crack, m/cycle; ,e eC n
– parameters of fracture
resistance of the metal pipeline;
IeK is intensity of
stresses, MPa (kgf/mm
2
). The intensity of the stresses is
proposed to be calculated taking into account the
geometry of the defect [4]. The calculation of the stress
intensity factor for an elliptic surface crack (Fig. 2) at
points A and B is determined by the following formulas:
,IA A A A
l
K M N S
Q
(15)
,IB B B B
l
K M N S
Q
(16)
1.65
1 1.464 ,Q (17)
where
3.25
3
1.5
1 0.89 0.57
A
N
,
MA 1.12 0.08 is a crack parameter at
point A, m; 2
1 0.32
B A
N N ; 1.23 0.09
B
M
is a crack parameter at point B; l is a crack depth, m; с
is a width of the crack, m; α = l/с at l ≤ с; r = l/t at
l ≤ 0.7 t.
Fig. 2. The scheme of a surface semi-elliptic fracture
with a curvature on the surface:
a along the axis Z; b along the Y axis
Changes in the mechanical properties of the metal
pipeline were taken into account with the help of the
following functions:
0.2 0.2
0.5
0.5
( ); ( )
( ); ( )
( ); ( )
( ); ( )
,
m m
A Z
a
m m a
R f t R f t
A f t Z f t
m f t a f t
R f t a f t
(18)
where is operating time, years; 0.2... mf f is empirical
function.
Mechanical properties of the metal of the main circulation pipe
Pipeline area Hardness
R
T
m
MPa
R
T
p0.2,
MPa
Z
Т
,
%
А
Т
, %
Thickness,
mm
Radius of
curvature,
mm
Main circulating pipeline
(“hot” thread)
167.6 55.10 41.79 66.67 27.64 78.29 495.0
The main church pipeline
(«cold» thread, section from Steam
Generator till Cerculating pump
168.0 55.28 41.91 66.60 27.55 78.45 495.0
Main circulating pipeline (“cold”
thread), section from main Cerculating
pump till hydraulic pump)
181.0 61.26 46.01 64.33 24.92 108.2 495.0
Pipeline connection collector with hot
thread of a loop No.4 Main
Circulation Circuit
168.4 55.46 42.04 66.53 27.46 39.98 213.0
a b
In Tablе provided mechanical properties of the HCT
metal and the communication line collector with the
“hot” thread loop No.4 Main Circulation Circuit and
geometric sizes of sites.
Fig. 3. Distribution of stresses 1-3 at the section of
the pipeline Main circulating pipeline, “hot” thread.
(Mode NO, load internal pressure)
Fourth stage. To conduct a calculation of stress
distribution in the pipeline (Fig. 3) depending on the
operating mode: NO, HT [5].
The fifth stage. To establish the correspondence
between the parameters of the technical condition and
the strength conditions [Р] of the pipelines in
accordance with the rules Norms of strength calculation
equipment [3].
The sixth stage. To determine the regularities of
changing the properties of the metal pipeline during
operation using the analysis of operational changes in
mechanical properties of the metal R
Т
m, R
Т
p0,2, Z
Т
, A
Т
,
KIC, and so on (see Fig. 3). To conduct a calculation on
the resistance to brittle fracture of the elements. The
mathematical models of the accumulation of fatigue
damage of equipment and pipelines from load operation
cycles in hard (19) and soft (20) symmetrical loading
modes, in hard (21) and soft (22) asymmetric loading
modes are proposed, taking into account the geometry
of the defect and changes in the mechanical properties
of the metal pipeline:
1
( )
( )
3
1 1
1
ln
1( ) /
( )
4
a
a
e
lc
xi i n
loo e ei i
a
i
f daza f N
f c K
e
E
, (19)
2
( )
( )
3
1 1
1
ln
1( ) /
( )
,
a
a
e
lcy
x
i i n
loo e ei i
a
i
f daza f N
f c K
e
E
(20)
(
) (
)
〈 〉
( )
( √
(
⁄
)
)
⁄ (∫
( )
)
, (21)
(
) (
)
〈 〉
( )
( √
⁄
)
⁄ (∫
( )
)
. (22)
The seventh stage. Forecasting of the limit
parameters of the technical state of the pipelines under
which the conditions of durability are not violated Plim =
[P]lim. At this stage, data from the results of stages 5 and
6 and dependency forecasting are used [Р](τ) and Р(τ)
taking into account the requirements of normative
documents [6] to the limit parameters of the pipelines
(Fig. 4).
To take into account the results of stages 5 and 6 and
forecast dependencies [Р](τ) and Р(τ) it is necessary to
add a condition. The figure follows the following. The
design documentation was planned at the level with the
loads, as well as the levels of radiation exposure and
vibration of the mechanisms and machines of the
nuclear power plant. This aggregate level of coercive
damage was introduced at design (dependence 1), which
was supposed to reduce the strength of the material of
the main pipeline by the dependence 2 over a period of
time from t0 till t1 from mark A to mark B1 ie up to level
Plim = [P]lim line 3.
In reality, the strength indicators for the time interval
from t0 till t1 dropped to the level В2. According to the
dependence 4, the reduction of the material strength of
the main pipeline, along the axis of ordinates, from t0 till
t1 decreased to magnitude АВ2. After this, we have a
total residual resource for strength (R) at the level:
2 1.R В В
(23)
Workinq time t, years
1
5
6
3
7
S
tr
e
n
q
th
i
n
d
ik
a
to
rs
,
М
P
а
P
re
d
ic
ta
b
le
d
a
m
a
q
e
p
a
ra
m
e
te
rs
,
1
0
м
А
В2
В1 С
-7
t0 t1 t2 t3
4
2
Fig. 4. Scheme of total impact on the material of the
main pipeline of the NPP, the power of the working
fluid body, radiation and vibration of mechanisms
and machines
The extrapolation of the strength of the material of
the main pipeline has shown that the level of marginal
strength [Plim], indicated by the straight 3 material will
reach at D. This means that we have a predicted residual
time resource tR., which is defined as follows:
3 1,Rt t t (24)
where t3 is projected time when the strength of the main
pipeline material is reduced to a level of ultimate
strength [Plim], MPa; t1 is the time at which, according to
the design calculations, should have fallen to the level
of marginal strength [Plim], MPa. This is likely to
happen only for two reasons, firstly, the actual level of
radiation exposure (see Fig. 4, dependence 5) was
significantly lower than expected, and secondly, the
properties of the resistivity of the main pipeline material
were significantly higher than expected (dependence 4).
Thus, the complex estimation of the calculations we
accept the level of damage (deviation of the size) of the
material of the main pipeline (see Fig. 4, dependence 6).
From Fig. 4 it follows that it is possible to operate a
nuclear power plant because the current value of
damage during the time interval from t1 to t3 is beyond
the level of the limit values, the boundary of which is on
line 7 (see Fig. 4). The condition for safe subsequent
operation of the NPP is the reduction of the permissible
load on the material of the main pipeline in the time
interval from t2 to t3.
The eighth stage. To conduct an assessment and
justification for conducting settlement investigations of
seismic influences on NPP equipment for safe operation
during a project earthquake and a maximum calculated
earthquake [7]. In Ukraine, the seismic environment is
attractive for the construction of a nuclear power plant,
but the earthquakes that took place in Romania and
Moldova in 1986, 1990, and in October 2018, affect the
seismic situation in Ukraine. In addition, the vibration
of mechanisms and machines on the NPP itself
constantly causes a slight but permanent damage to the
main pipeline of the NPP. In addition, at such plants as
the NPP, the material of the main pipeline constantly
has a certain level of radiation exposure. Therefore,
combine the destructive effect of radiation irradiation,
the effect of vibration of mechanisms and machines, and
the effect of liquid pressure on the material of the main
pipeline NPP mean dependence 4 (Fig. 5).
In this work, the mathematical model of the
accumulation of fatigue damage to equipment and
pipelines from load operation cycles during hard (16)
and soft (17) symmetrical loading modes, with hard (18)
and soft (19) asymmetric load modes taking into
account the geometry of the defect and the mechanical
properties of the metal pipeline. According to the results
of the research, the dependence of the damage to the
main pipeline of the NPP during load operating cycles
under conditions of strict symmetric loading regime and
with additional influence of the project earthquake and
with the maximum calculated earthquake were
constructed (see Fig. 5).
Time t, years
2
4
3
S
tr
en
th
in
di
ka
to
rs
, М
P
а
P
re
di
ct
ab
le
d
am
aq
e
pf
rf
m
et
er
s
, 1
0
м
А
В2
-7
t0 t1 t2 t3
1
57
6
С1
С2
Fig. 5. Impact of seismic situations
on NPP equipment damage
From Fig. 5, it follows that in other equal conditions
(that is, in the presence of the projected residual
resource for the strength of the material of the main
pipeline), the level of its damage in the rigid mode of
loading, taking into account the average speed of the
defect and the average mechanical properties of the
metal of the pipeline (interval of time from t1 tо t3) –
dependence 4 (see Fig. 5). Curves 5 and 6 were also
constructed, which show the effect of additional seismic
activity on damage to the material of the main pipeline.
Thus, it was determined that after the first seismic
activity the dependence of the damage from time to time
was changed by the dependence 5, and after the second
seismic activity by the dependence 6. From Fig. 5 also
suggests that less safer seismic activity takes place in
the initial period of existence of the projected residual
resource, and in the final period of the projected residual
resource, seismic activity is dangerous, as a sharp
increase in the level of damage from seismic activity
leads to exceeding the limit of permissible level of
damage to NPP equipment.
CONCLUSIONS AND PERSPECTIVES
OF FURTHER RESEARCH
As a result of the conducted research, the following
conclusions can be drawn that a comprehensive solution
to the problem of quality improvement and extension of
the lifetime of power units should begin with the
implementation of over-design works in the following
areas: analysis of statistical data on the reliability and
efficiency of equipment operation; creation of databases
of groups and elements of equipment, their ranking
according to the degree of criticality; development of
criteria for quality and methods for determining the
m
m
m
residual resource; examination, qualification, definition
of residual resource of buildings, structures, foundations
and metal structures taking into account geotechnical
and seismotectonic conditions; development of methods
for optimizing operating modes of equipment in order to
reduce the rate of damage (resource consumption rate)
of critical elements of equipment; development of
methods for technical diagnostics, monitoring and
monitoring of the technical condition and the remaining
resource of equipment.
REFERENCES
1. Г.С. Кіпоренко, М.Є. Пахалович, О.М. Хоро-
шилов. Оцінка технічного стану трубопровідних
систем АЕС на відповідність нормативним
параметрам // Системи управління, навігації та
зв'язку. 2016, №4, c. 146-152.
2. М.Є. Пахалович, Г.С. Кіпоренко. Вдоско-
налення методики розрахунку опору крихкому
руйнуванню трубопроводів Південно-Української
АЕС // Системи обробки інформації. 2016, №7,
c. 181-184.
3. ПНАЭ Г-7-002-86. Нормы расчета на
прочность оборудования и трубопроводов атомных
энергетических установок.
4. Г.С. Кіпоренко. Удосконалення нормативного
забезпечення експлуатаційної безпеки
трубопровідних систем атомних електростанцій:
Aвтореф. дис. ... канд. техн. наук. Харків: Укра-
їнська інженерно-педагогічна академія, 2010, 20 c.
5. П.Н. Демидов, А.И. Трубаев. Прогно-
зирование остаточного ресурса трубопроводов с
учетом эрозионно-коррозионного износа // Вісник
НТУ «ХПІ». 2011, №12, c. 23-31.
6. СОУ НАЕК 033:2012. Техническое
обслуживание и ремонт. Правила организации
технического обслуживания и ремонта систем и
оборудования атомных электростанций.
7. ПНАЭ Г-5-006-87. Нормы проектирования
сейсмостойких атомных станций.
Article received 21.03.2019
АЛГОРИТМ ТЕХНИЧЕСКОЙ ДИАГНОСТИКИ КОМПЛЕКСА НАКОПЛЕННЫХ ПОВРЕЖДЕНИЙ
ДЛЯ ПРОДЛЕНИЯ РЕСУРСА ЦИРКУЛЯЦИОННОГО ТРУБОПРОВОДА АЭС
А. Гринченко, Р. Трищ, В. Бурдейная, С. Челишева
Исследуются качество и безопасность эксплуатации главного циркуляционного трубопровода атомной
электростанции с целью продления ресурса трубопроводов реакторного отделения АЭС на основе
разработки научно обоснованной математической модели и алгоритма их технической диагностики.
Предложена комплексная оценка качества эксплуатации трубопроводных систем путем учета особенностей
их напряженно-деформированного состояния и сейсмостойкости. Целью статьи является обоснование
комплексной оценки качества и безопасности эксплуатации трубопроводов реакторного отделения АЭС на
основе разработки научно обоснованной математической модели и алгоритма их технической диагностики с
целью продления срока эксплуатации. Методы исследования: расчеты с помощью математической модели;
сравнение результатов вычисления, прогнозирования предельных параметров технического состояния и
мониторинг механических свойств материала магистрального трубопровода; обследование, квалификация,
определение остаточного ресурса зданий, сооружений, фундаментов и металлоконструкций с учетом
геотехнических и сейсмотектонических условий. Определено, что в начальный период существования
прогнозируемого остаточного ресурса сейсмическая активность в зоне 300...500 км от расположения АЭС
менее безопасная, чем сейсмическая активность, которая проходит в заключительный период
прогнозируемого остаточного ресурса, так как резкое повышение уровня повреждения от сейсмической
активности приводит к превышению предела допустимого уровня повреждения материала магистрального
трубопровода.
АЛГОРИТМ ТЕХНІЧНОЇ ДІАГНОСТИКИ КОМПЛЕКСУ НАКОПИЧЕНИХ ПОШКОДЖЕНЬ
ДЛЯ ПОДОВЖЕННЯ РЕСУРСУ ЦИРКУЛЯЦІЙНОГО ТРУБОПРОВОДУ АЕС
Г. Грінченко, Р. Тріщ, В. Бурдейна, С. Челишева
Досліджуються якість та безпека експлуатації головного циркуляційного трубопроводу атомної
електростанції з метою подовження ресурсу трубопроводів реакторного відділення АЕС на основі розробки
науково обґрунтованої математичної моделі та алгоритму їх технічної діагностики. Запропоновано
комплексну оцінку якості експлуатації трубопровідних систем шляхом врахування особливостей їх
напружено-деформованого стану та сейсмостійкості. Метою статті є обґрунтування комплексної оцінки
якості та безпеки експлуатації трубопроводів реакторного відділення АЕС на основі розробки науково
обґрунтованої математичної моделі та алгоритму їх технічної діагностики з метою продовження терміну
експлуатації. Методи дослідження: розрахунки за допомогою математичної моделі; порівняння результатів
обчислення, прогнозування граничних параметрів технічного стану та моніторинг механічних властивостей
матеріалу магістрального трубопроводу; обстеження, кваліфікація, визначення залишкового ресурсу
будівель, споруд, фундаментів і металоконструкцій з урахуванням геотехнічних і сейсмотектонічних умов.
Визначено, що в начальний період існування прогнозованого залишкового ресурсу сейсмічна активність у
зоні 300…500 км від розташування АЕС є менш безпечніша, ніж сейсмічна активність, яка проходить у
завершальний період прогнозованого залишкового ресурсу, так як різке підвищення рівня пошкодження від
сейсмічної активності призводить до перевищення межі допустимого рівня пошкодження матеріалу
магістрального трубопроводу.
http://www.irbis-nbuv.gov.ua/cgi-bin/irbis64r_81/cgiirbis_64.exe?Z21ID=&I21DBN=REF&P21DBN=REF&S21STN=1&S21REF=10&S21FMT=fullwebr&C21COM=S&S21CNR=20&S21P01=0&S21P02=0&S21P03=TJ=&S21COLORTERMS=1&S21STR=%D0%A1%D0%B8%D1%81%D1%82%D0%B5%D0%BC%D0%B8%20%D1%83%D0%BF%D1%80%D0%B0%D0%B2%D0%BB%D1%96%D0%BD%D0%BD%D1%8F,%20%D0%BD%D0%B0%D0%B2%D1%96%D0%B3%D0%B0%D1%86%D1%96%D1%97%20%D1%82%D0%B0%20%D0%B7%D0%B2%27%D1%8F%D0%B7%D0%BA%D1%83
http://www.irbis-nbuv.gov.ua/cgi-bin/irbis64r_81/cgiirbis_64.exe?Z21ID=&I21DBN=REF&P21DBN=REF&S21STN=1&S21REF=10&S21FMT=fullwebr&C21COM=S&S21CNR=20&S21P01=0&S21P02=0&S21P03=TJ=&S21COLORTERMS=1&S21STR=%D0%A1%D0%B8%D1%81%D1%82%D0%B5%D0%BC%D0%B8%20%D1%83%D0%BF%D1%80%D0%B0%D0%B2%D0%BB%D1%96%D0%BD%D0%BD%D1%8F,%20%D0%BD%D0%B0%D0%B2%D1%96%D0%B3%D0%B0%D1%86%D1%96%D1%97%20%D1%82%D0%B0%20%D0%B7%D0%B2%27%D1%8F%D0%B7%D0%BA%D1%83
http://www.irbis-nbuv.gov.ua/cgi-bin/irbis_nbuv/cgiirbis_64.exe?Z21ID=&I21DBN=UJRN&P21DBN=UJRN&S21STN=1&S21REF=10&S21FMT=JUU_all&C21COM=S&S21CNR=20&S21P01=0&S21P02=0&S21P03=IJ=&S21COLORTERMS=1&S21STR=%D0%9670474
|
| id | nasplib_isofts_kiev_ua-123456789-194949 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T16:24:12Z |
| publishDate | 2019 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Hrinchenko, H. Trisch, R. Burdeina, V. Chelysheva, S. 2023-12-01T18:36:12Z 2023-12-01T18:36:12Z 2019 Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant / H. Hrinchenko, R. Trisch, V. Burdeina, S. Chelysheva // Problems of atomic science and technology. — 2019. — № 2. — С. 104-110. — Бібліогр.: 7 назв. — англ. 1562-6016 https://nasplib.isofts.kiev.ua/handle/123456789/194949 621.311:621.313 The quality and safety of operation of the main circulating pipeline of the nuclear power plant is being studied in order to extend the life of the pipelines of the reactor unit of the NPP on the basis of the development of a scientifically sound mathematical model and algorithm for their technical diagnostics. The complex estimation of the quality of operation of pipeline systems is proposed, taking into account the peculiarities of their stress-strain state and seismic stability. The purpose of the article is to substantiate the integrated assessment of the quality and safety of operation of pipelines of the reactor unit of the NPP on the basis of the development of a scientifically sound mathematical model and algorithm for their technical diagnostics in order to extend the life of the operation. Research methods: calculations by mathematical model, comparison of results of calculation, forecasting of boundary parameters of technical condition and monitoring of mechanical properties of main pipeline material, inspection, qualification, determination of residual resource of buildings, structures, foundations and metal structures taking into account geotechnical and seismotectonic conditions. It is determined that in the initial period of existence of the projected residual resource seismic activity in the zone 300...500 km from the location of the NPP is less safe than seismic activity, which takes place in the final period of the projected residual resource, as a sharp increase in the level of damage from seismic activity leads to exceeding the limit of permissible the level of damage to the material of the main pipeline. Досліджуються якість та безпека експлуатації головного циркуляційного трубопроводу атомної електростанції з метою подовження ресурсу трубопроводів реакторного відділення АЕС на основі розробки науково обґрунтованої математичної моделі та алгоритму їх технічної діагностики. Запропоновано комплексну оцінку якості експлуатації трубопровідних систем шляхом врахування особливостей їх напружено-деформованого стану та сейсмостійкості. Метою статті є обґрунтування комплексної оцінки якості та безпеки експлуатації трубопроводів реакторного відділення АЕС на основі розробки науково обґрунтованої математичної моделі та алгоритму їх технічної діагностики з метою продовження терміну експлуатації. Методи дослідження: розрахунки за допомогою математичної моделі; порівняння результатів обчислення, прогнозування граничних параметрів технічного стану та моніторинг механічних властивостей матеріалу магістрального трубопроводу; обстеження, кваліфікація, визначення залишкового ресурсу будівель, споруд, фундаментів і металоконструкцій з урахуванням геотехнічних і сейсмотектонічних умов. Визначено, що в начальний період існування прогнозованого залишкового ресурсу сейсмічна активність у зоні 300…500 км від розташування АЕС є менш безпечніша, ніж сейсмічна активність, яка проходить у завершальний період прогнозованого залишкового ресурсу, так як різке підвищення рівня пошкодження від сейсмічної активності призводить до перевищення межі допустимого рівня пошкодження матеріалу магістрального трубопроводу. Исследуются качество и безопасность эксплуатации главного циркуляционного трубопровода атомной электростанции с целью продления ресурса трубопроводов реакторного отделения АЭС на основе разработки научно обоснованной математической модели и алгоритма их технической диагностики. Предложена комплексная оценка качества эксплуатации трубопроводных систем путем учета особенностей их напряженно-деформированного состояния и сейсмостойкости. Целью статьи является обоснование комплексной оценки качества и безопасности эксплуатации трубопроводов реакторного отделения АЭС на основе разработки научно обоснованной математической модели и алгоритма их технической диагностики с целью продления срока эксплуатации. Методы исследования: расчеты с помощью математической модели; сравнение результатов вычисления, прогнозирования предельных параметров технического состояния и мониторинг механических свойств материала магистрального трубопровода; обследование, квалификация, определение остаточного ресурса зданий, сооружений, фундаментов и металлоконструкций с учетом геотехнических и сейсмотектонических условий. Определено, что в начальный период существования прогнозируемого остаточного ресурса сейсмическая активность в зоне 300...500 км от расположения АЭС менее безопасная, чем сейсмическая активность, которая проходит в заключительный период прогнозируемого остаточного ресурса, так как резкое повышение уровня повреждения от сейсмической активности приводит к превышению предела допустимого уровня повреждения материала магистрального трубопровода. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Thermal and fast reactor materials Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant Алгоритм технічної діагностики комплексу накопичених пошкоджень для подовження ресурсу циркуляційного трубопроводу АЕС Алгоритм технической диагностики комплекса накопленных повреждений для продления ресурса циркуляционного трубопровода АЭС Article published earlier |
| spellingShingle | Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant Hrinchenko, H. Trisch, R. Burdeina, V. Chelysheva, S. Thermal and fast reactor materials |
| title | Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant |
| title_alt | Алгоритм технічної діагностики комплексу накопичених пошкоджень для подовження ресурсу циркуляційного трубопроводу АЕС Алгоритм технической диагностики комплекса накопленных повреждений для продления ресурса циркуляционного трубопровода АЭС |
| title_full | Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant |
| title_fullStr | Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant |
| title_full_unstemmed | Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant |
| title_short | Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant |
| title_sort | algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant |
| topic | Thermal and fast reactor materials |
| topic_facet | Thermal and fast reactor materials |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/194949 |
| work_keys_str_mv | AT hrinchenkoh algorithmoftechnicaldiagnosticsofthecomplicateddamagetothecontinuedresourceofthecirculationpipelineofthenuclearpowerplant AT trischr algorithmoftechnicaldiagnosticsofthecomplicateddamagetothecontinuedresourceofthecirculationpipelineofthenuclearpowerplant AT burdeinav algorithmoftechnicaldiagnosticsofthecomplicateddamagetothecontinuedresourceofthecirculationpipelineofthenuclearpowerplant AT chelyshevas algorithmoftechnicaldiagnosticsofthecomplicateddamagetothecontinuedresourceofthecirculationpipelineofthenuclearpowerplant AT hrinchenkoh algoritmtehníčnoídíagnostikikompleksunakopičenihpoškodženʹdlâpodovžennâresursucirkulâcíinogotruboprovoduaes AT trischr algoritmtehníčnoídíagnostikikompleksunakopičenihpoškodženʹdlâpodovžennâresursucirkulâcíinogotruboprovoduaes AT burdeinav algoritmtehníčnoídíagnostikikompleksunakopičenihpoškodženʹdlâpodovžennâresursucirkulâcíinogotruboprovoduaes AT chelyshevas algoritmtehníčnoídíagnostikikompleksunakopičenihpoškodženʹdlâpodovžennâresursucirkulâcíinogotruboprovoduaes AT hrinchenkoh algoritmtehničeskoidiagnostikikompleksanakoplennyhpovreždeniidlâprodleniâresursacirkulâcionnogotruboprovodaaés AT trischr algoritmtehničeskoidiagnostikikompleksanakoplennyhpovreždeniidlâprodleniâresursacirkulâcionnogotruboprovodaaés AT burdeinav algoritmtehničeskoidiagnostikikompleksanakoplennyhpovreždeniidlâprodleniâresursacirkulâcionnogotruboprovodaaés AT chelyshevas algoritmtehničeskoidiagnostikikompleksanakoplennyhpovreždeniidlâprodleniâresursacirkulâcionnogotruboprovodaaés |