US2017321879A1PendingUtilityA1
Horizontal Steam Generator for a Reactor Plant with a Water-Cooled Water-Moderated Power Reactor and a Reactor Plant with the said Steam Generator
Assignee: AKTSYONERNOE OBSHCHESTIVO ORDENA TRUDOVOGO KRASNOGO ZNAMENI I ORDENA TRUDA CHSSR OPYTNOEPriority: Dec 12, 2014Filed: Dec 9, 2015Published: Nov 9, 2017
Est. expiryDec 12, 2034(~8.3 yrs left)· nominal 20-yr term from priority
F22B 37/002F22B 37/22F22B 37/228F22B 29/06F22B 1/02F28F 9/0132F22B 1/023F28D 2021/0064F28D 7/16F22B 1/162F22B 37/02Y02E30/30Y02E30/00
13
PatentIndex Score
0
Cited by
0
References
0
Claims
Abstract
This invention relates to electric power industry, and more particularly to horizontal steam generators for nuclear power plants with a water-cooled water-moderated power reactor (VVER) and to reactor plants with a VVER reactor and a horizontal steam generator. A reactor plant with a VVER reactor and a horizontal seam generator, including a nuclear reactor with four circulation loops, each comprising a steam generator with a horizontal bundle of heat-exchange tubes divided into banks by means of inter-tubular tunnels and connected to primary circuit coolant headers inside a cylindrical pressure vessel with elliptical bottoms, a reactor coolant pump, and a primary circuit coolant main circulation pipeline.
Claims
exact text as granted — not AI-modified1 . A horizontal steam generator for a reactor plant with a water-cooled water-moderated power reactor comprising a cylindrical pressure vessel equipped at least with one feed water supply connection pipe and one steam removal connection pipe, and two elliptical bottoms, internals, primary circuit coolant inlet and outlet headers connected to a heat-exchange tube bundle forming a steam-generator heat-exchange surface, the heat-exchange tube bundle being divided into banks by intertubular tunnels, wherein distance S between the primary circuit coolant header centerlines in the transverse direction of the steam generator pressure vessel has been selected based on the following ratio:
0.4
≤
S
D
vess
≤
0.6
,
where D vess is the steam generator pressure vessel inner diameter, and steam generator length L v along the inner surfaces of the elliptical bottoms has been selected based on the following ratio:
L
κ
=
D
head
+
2
·
[
(
ctg
(
α
2
)
-
1
sin
(
α
2
)
)
·
(
B
1
2
+
B
2
+
(
π
·
D
head
4
·
S
head
-
1
)
·
S
h
)
+
(
π
·
D
head
4
·
S
head
-
1
)
·
S
h
·
1
sin
(
α
2
)
+
Δ
]
+
H
hes
·
10
6
π
·
d
·
N
tb
,
where: D head is the coolant header outer diameter in the drilled part, mm,
α is the heat-exchange tube central bend angle, deg.,
B 1 is the width of the heat-exchange tube central intertubular tunnel, mm,
B 2 is the width of the heat-exchange tube intertubular tunnel opposite to the coolant header, mm,
S head is the heat-exchange tube circumferential spacing on the outer surface of the coolant header, mm,
Sh is the spacing between heat-exchange tubes in the horizontal heat-exchange bundle row, mm,
H hes is the steam generator heat-exchange surface area, m 2 ,
N tb is the number of steam generator heat-exchange tubes, pcs.,
d is the outer heat-exchange tube diameter, mm,
Δ is the distance from the outer heat-exchange bundle tube to the steam generator bottom inner surface along the longitudinal steam generator axis, in mm, wherein central heat-exchange tube bend angle α and distance Δ have been selected from the following ranges: 90°≦α≦150° and 300≦Δ≦1000 mm.
2 . A steam generator according to claim 1 , wherein the heat-exchange tube bundle is filled with heat-exchange tubes from bottom upwards evenly with vertical gaps between adjacent tubes not exceeding the vertical spacing of tubes in the bundle.
3 . A steam generator according to claim 1 , wherein the vertical intertubular tunnel width is between 100 mm and 250 mm.
4 . A steam generator according to claim 1 , wherein the heat-exchange tube bend at the point of connection to the coolant header shall have a radius of at least 60 mm and, preferably, at least 100 mm.
5 . A steam generator according to claim 1 , wherein the coolant header drilling area shall exceed the area of the holes for connection of heat-exchange tubes to the same by at least 20%.
6 . A reactor plant with a water-cooled water-moderated power reactor and a horizontal seam generator, including a nuclear reactor with four circulation loops, each comprising a steam generator with a horizontal bundle of heat-exchange tubes divided into banks by means of intertubular tunnels and connected to primary circuit coolant headers inside a cylindrical pressure vessel with elliptical bottoms, a reactor coolant pump, and a primary circuit coolant main circulation pipeline, wherein pressure vessel bore D vess , distance S between the centerlines of the primary circuit coolant headers in the transverse direction and steam generator length L v along the inner surfaces of the elliptical bottoms have been respectively selected based on the following ratios:
0.148
·
D
+
0.637
·
0.054
·
D
2
+
3.142
·
N
tb
·
S
h
·
S
v
k
≤
D
vess
≤
1.827
·
H
,
0.4
≤
S
D
vess
≤
0.6
,
L
κ
=
D
head
+
2
·
[
(
ctg
(
α
2
)
-
1
sin
(
α
2
)
)
·
(
B
1
2
+
B
2
+
(
π
·
D
head
4
·
S
head
-
1
)
·
S
h
)
+
(
π
·
D
head
4
·
S
head
-
1
)
·
S
h
·
1
sin
(
α
2
)
+
Δ
]
+
H
hes
·
10
6
π
·
d
·
N
tb
,
where: D is the rated steam generator capacity, t/h,
N tb is the number of steam generator vessel heat-exchange tubes, pcs.,
Sv, Sh is the spacing between heat-exchange tubes in vertical and horizontal rows of heat-exchange bundle, respectively, mm,
k is the arrangement identifier of heat-exchange tube bundle in a bank (k=1 for in-line arrangement and k=2 for staggered arrangement),
H is the steam generator vessel tube filling height, mm,
D head is the primary circuit header outer diameter in the drilled area, mm,
α is the heat-exchange tube central bend angle, deg.,
B 1 is the width of the heat-exchange tube central tunnel, mm,
B 2 is the width of the heat-exchange tube tunnel opposite to the coolant header, mm,
S head is the heat-exchange tube circumferential spacing on the outer surface of the coolant header, mm,
H hes is the steam generator heat-exchange surface area, m 2 ,
d is the outer heat-exchange tube diameter, mm,
Δ is the distance from the outer heat-exchange bundle tube to the steam generator bottom inner surface along the longitudinal steam generator axis, in mm, wherein heat-exchange tube bend angle α and distance Δ have been selected from the following ranges:
90°≦α≦150° and 300 mm≦Δ≦1000 mm.
7 . A reactor plant according to claim 6 , wherein the steam generator and the reactor coolant pump are connected to the reactor building walls by hydraulic snubbers.
8 . A reactor plant according to claim 6 , wherein the reactor coolant pump is installed downstream of the steam generator along the primary circuit coolant flow in the circulation loop.
9 . A reactor plant according to claim 6 , wherein the reactor coolant pump is installed both on the hot leg and the cold leg of the main circulation pipeline in the circulation loop.
10 . A reactor plant according to claim 6 , wherein two reactor coolant pumps are installed in parallel on the cold leg of the main circulation pipeline.
11 . A reactor plant according to claim 6 , wherein gate valves are installed on the main circulation pipeline legs.Join the waitlist — get patent alerts
Track US2017321879A1 — get alerts on status changes and closely related new filings.
We store only your email — no account needed. See our privacy policy.