US 2017/0321879 A1Published application

Horizontal Steam Generator for a Reactor Plant with a Water-Cooled Water-Moderated Power Reactor and a Reactor Plant with the said Steam Generator

AssigneeAktsyonernoe Obshchestivo "Ordena Trudovogo Krasnogo Znameni I Ordena Truda Chssr Opytnoe

InventorsDmitriy Aleksandrovich LAKHOV, Aleksey Vladimirovich SAFRONOV

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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.

Claims11

Dependent claims

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 Dvess is the steam generator pressure vessel inner diameter, and steam generator length Lv 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:
Dhead is the coolant header outer diameter in the drilled part, mm,
α is the heat-exchange tube central bend angle, deg.,
B1 is the width of the heat-exchange tube central intertubular tunnel, mm,
B2 is the width of the heat-exchange tube intertubular tunnel opposite to the coolant header, mm,
Shead 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,
Hhes is the steam generator heat-exchange surface area, m2,
Ntb 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.

108 more elements

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 Dvess, distance S between the centerlines of the primary circuit coolant headers in the transverse direction and steam generator length Lv 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,
Ntb 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,
Dhead is the primary circuit header outer diameter in the drilled area, mm,
α is the heat-exchange tube central bend angle, deg.,
B1 is the width of the heat-exchange tube central tunnel, mm,
B2 is the width of the heat-exchange tube tunnel opposite to the coolant header, mm,
Shead is the heat-exchange tube circumferential spacing on the outer surface of the coolant header, mm,
Hhes is the steam generator heat-exchange surface area, m2,
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.

143 more elements

Dependencies are inferred from the claim text.

Facts

Application: 15/535,360Filed 9 Dec 2015
Priority: RU 201415042712 Dec 2014
Published: 9 Nov 2017
Term ends: Not estimatedThe source records don’t support an estimate.

Classification10 codes

F22B 1/023
By exploitation of the heat content of hot heat carriers: with heating tubes for nuclear reactors, as long as they are not classified according to…
F22B 1/162
The heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour: in combination with a nuclear installation
F22B 29/06
Steam boilers of forced-flow type: of once-through type, i.e. built-up from tubes receiving water at one end and delivering superheated steam at…
F22B 37/002
Component parts or details of steam boilers: specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment…