CA1183286A - Coolant manifold for fusion reactor blanket - Google Patents

Coolant manifold for fusion reactor blanket

Info

Publication number
CA1183286A
CA1183286A CA000405436A CA405436A CA1183286A CA 1183286 A CA1183286 A CA 1183286A CA 000405436 A CA000405436 A CA 000405436A CA 405436 A CA405436 A CA 405436A CA 1183286 A CA1183286 A CA 1183286A
Authority
CA
Canada
Prior art keywords
manifold
coolant
blanket
module
duct
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
CA000405436A
Other languages
French (fr)
Inventor
Robert R. Holman
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
CBS Corp
Original Assignee
Westinghouse Electric Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Application granted granted Critical
Publication of CA1183286A publication Critical patent/CA1183286A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B1/00Thermonuclear fusion reactors
    • G21B1/11Details
    • G21B1/13First wall; Blanket; Divertor
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Nuclear fusion reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

ABSTRACT OF THE DISCLOSURE
A coolant manifold system for distribution of cool coolant to, and collection of hot coolant from, a heat source such as the blanket of a fusion reactor.
The manifold system comprises a number of mani-fold modules disposed around the blanket corresponding to blanket subdivisions. Each manifold has an inner duct with hot, low-pressure fluid flow therethrough and an outer duct with cool, high-pressure flow therethrough. A
liner in the inner duct insulates the walls of the inner duct and thereby lowers structural component temperatures, which assists in the support of the manifold. The overall pressurization of the manifold causes the manifold to resist deformation and increases manifold structural strength.

Description

~3~

1 48,221 COOLANT MANIFOLD EOR FUSION REACTOR BLANKET
BACKGROUND OF THE INVENTION
This invention is a distribution manifold in-tended to provide coolant flow to a heat source, as for example, the blanket of a ~usion reactor system, espe-cially a Tokamak segmented fusion reactor blanket.
The fusion reaction in a fusion reactor deposits energy in a structure surrounding the plasma called a blanket. The blanket is itself cooled, and energy removed therefrom, by a fluid coolant ~low, usually a flow of an inert gas such as helium. A flow distribution manifold to distribute coolant flow to the blanket is difficult to build due to a number of desired features and functions of the system, particularly as adapted to service a doughnut-shaped, Tokamak reactor. Because the blanket re~uires lS frequent maintenance, the coolant manifold must not pre-clude access thereto, or alternatively the manifold must be capable of speedy removal and replacement. The mani-fold should be tolerant of deformations and deflections associated with cyclic, long term, high radiation doses and high temperature operation. Since it is not desired to generate a large mass of radioactive material by ex-posure to plasma radiation, the manifold should have a minimum bulk and yet be strong and as leak-tight as possi ble.
Due to non spherical, non-cylindrical geometry imposed by the Tokamak configuration, the manifold does not exhibit strength as a result of a favorable structural shape.

~3~
2 48,221 Conse~uently, it is desired to provide a mani-fold for distributing coolant flow to a blanket which manifold is of minimum bulk, strong, and capable of rapid disasse~ly.
SUMMARY OF THE INVENTION
The invented coolant manifold uses modules, a number of which can be grouped together to form a complete manifold system. Each module has an inner duct containing a fl.ow stream of hot coolant at a relatively low pressure and an outer duct of cooler fluid at a higher pressure.
The structural components of the module comprising most of the material bulk of the manifold are located in the outer duct. An inner liner insulates the hot inner duct from the cooler outer duct, increasing the temperature dif-ference between these two regions.
The overall strength of the module is augmented by the internal gas pressurization of the module. Also, the cooler temperatures existing in the outer duct enable the use of less bulky structural members since better material properties occur at lower temperatures.
Due to the module character of the manifold, disassembly is a quick and simple process.
BR~EF DESCRIPTION OF THE DRAWINGS
Figure 1 is a plan schematic of the general 2S arrangement of a TOKAMAK reactor;
Figure 2 is a detail from Figure l;
Figure 3 is a partially sectioned schematic of a portion of the manifold and blanket;
Figure 4 is an enlarged detail ~rom Figure 3;
Figures 5 and 6 are schematics of the manifold;
and Figure 7 is a schematic section of th~ manifold.
DETAILED DESCRIPTION
A series of semicircular or otherwise appropri-ately curved manifold modules are grouped together such that the surface of the blanket is entirely or substan-tially covered. Each module has a coolant inlet at one
3 48,221 end and an outlet at the other end. In traversing the module, the coolant passes through a path which forces coolant flow, at intervals along the module, to ~low through adjacent blanket sections, thereby removing blan-ket heat.
The modules are attached to the blanket by a quick release type of fitting. The fitting, when instal-led, maintains sufficient contact pressure between the module and the blanket section such that a seal is estab-lished between the flow connections as discussed later.
Figure l shows the general arrangement of thetorus of a TOKAMAK fusion reactor. A plurality of blanket sections 21, are dispersed about the torus 2 such that most or all of the outer surface of the torus 2 is cover-ed. Only a few sections 21 are show in section in Figure1 for clarity. Electromagnetic coils 20 surround blanket sections 21, shields 22, and manifolds 1, restricting access.
Manifolds 1 function to distribute coolant flow to sections 21 of the blanket. Figures 2 and 3 show how the blanket itself comprises a series of sections 21 each of which is provided with coolant flow. Blanket sections 21 which are disposed axially in one plane are served by one manifold module 1 as shown in Figure 2 (except that a number of modules 1 are necessary to circumscribe torus 2). Inlet pipe 3 and outlet pipe 4 supply manlfold module 1 with coolant flow from headers (not shown) common to all modules 1 or individual to each module 1.
Figure 4 is an enlarged detail from Figure 3.
Module 1 is attached to blanket section 21 by fitting 26 acting on ridges 6 on blanket section 21 and module 1.
This fitting 26 maintains sealing contact between a blan-ket nozzle 28 and an inner duct hole 18 at seat surface 27, and similar sealing contact at surface 29.
Refer to Figures 5 and 7. Manifold module 1 is appro~imately rectangular in cross section. A central duct 7 of manifold 1 is provided to contain and channel
4 48,221 flow returning from blanket section 21 where the coolant has been heated by radiation energy from the fusi~n re-action.
Manifold 1 has cold ducts 12 intended to channel coolant flow prior to entry into blanket section 21. Cold ducts 12 are partially formed by webs 13 which have open-ings 14 to provide for fluid communication between all cold ducts 12. Central duct 7 also has perforated webs 15 which may or may not be required, dependent upon the hot gas return pressure.
Refer to Figure 5. This plan view of manifold 1 is taken at an elevation (see Fig. 6) chosen to pass through a site where fluid communication between manifold 1 and blanket section 21 occurs. At each such site, manifold 1 has a large outer hole 16 in outer manifold 1 wall 17 and a smaller inner hole 18 in duct wall 10 of lnner duct 7. These holes 16 and 18 are also shown in Flgure ~ rt is intended that nozzle 28 (see Fig. L~) mounted on blanket section 21 mate to and seal with hole 18 when attachment between manifold 1 and blanket section
5 is accomplished using fitting 26 (in Figure L~). Accord-ing to the design and needs of blanket section 21, sets of holes 16 and 18, centered in rectangular patterns of ridge
6 (see Figure 6), are spaced intermittently along manifold 1, fluch that each blanket section 21 has one set.

~' ,,,~ .~,"

48,2~1 The coolaIIt flow path is as follows: rel~tively cool, high-pressure coolant is pumped into inlet pipe 3 (see Figure 2), flowing into module 1. This flow stream is directed into cold ducts 12 by inlet pipe 3. Coolant flows through cold ducts 12 and is distributed to a par-allel combination of flow paths through as many holes 16 and blanket nozzles 28 as may be needed in a particular blanket design. The coolant is heated in blanket sections 5 (follow flow arrows in Fig. 4) and returns to hole 18 via nozzle 2~. This heated coolant then passes via hot central duct 7 to outlet pipe 4 (see Fig. 2).
Flow through the central duct 7 may be antony-mous or parallel to flow through cold ducts 12 (by re-location of outlet pipe 4) but preferably is so arranged as to be complementary to natural circulation flow pat-terns. (Hot coolant stream disposed to rise vertically with respect to gravity, cold stream contrary).
The coolant flow in central duct 7 is at a higher temperature than the coolant flow in the cold ducts 12 due to blanket heating. The coolant flow in central duct 7 is at a lower pressure than the coolant flow in the cold ducts 12 due to blanket section 21 pressure resist-ance and the pressure resistance of holes 16 and 18.
Despite lower pressure in central duct 7, the ~5 struct~lre is not free to relieve stresses in cold ducts 12 by deformation in the radially inward direction toward the ce.ntral duct 7 because this duct 7 may have structural web.s 13 if necessary.
Deformation of the manifold module 1 is opposed b~ wall and web stresses due to internal pressurization.
The exposure of most structural webs and walls to lower temperatures (enhanced by liner 8) improves the material properties of the module.
Thus, pressure and temperature characteristics o manifold l are of significant advantage in augmenting structural strength and reducing material requirements.

6 48,221 The manifold 1 can be detached from inlet and outlet pipes 3 and 4 and removed individually from blanket sections 21 or even left attached to sections 21 if these are to be removed and replaced.
The description of the manifold in the above specification and drawings is susceptible to various modifications without departure from the spirit and scope of the invention. For example, the manifold module as disclosed may, in fact, be a composite of smaller sections attached together. Therefore, this specification should be interpreted as illustrative rather than limiting.

Claims

I claim:
A sectioned, light weight coolant manifold for the distribution of relatively cool high-pressure coolant and heated, lower-pressure coolant respectively to and from a plurality of torus-shaped fusion reactor blanket sections, said manifold comprising:
a plurality of semicircular modules, sufficient in number to provide for all blanket sections, each semicircular module having:
(a) quick release means for attachment to said blanket sections;
(b) a cool coolant inlet nozzle at one end of said module for inlet of cool, high-pressure coolant;
(c) a heated coolant outlet nozzle at a second end of said module for outlet of heated, lower-pressure coolant;
(d) an outer duct surrounding and supporting an inner duct, both ducts extending the length of said module, the inner duct in fluid communication with the outlet nozzle, and the outer duct in fluid communication with the inlet nozzle;
(e) a plurality of paired holes along the module length, grouped in pairs of two, each pair having a hole from the outer duct and a hole from the inner duct, the pairs being flow paths to blanket sections, allowing cool coolant flow to exit from the module, pass through a blanket section, and return to the inner duct, the flow paths to the holes being directed by blanket section components, said manifold being of light weight as a consequence of resistance to deformation of the semicircular module due to internal coolant pressurization.
CA000405436A 1981-06-29 1982-06-17 Coolant manifold for fusion reactor blanket Expired CA1183286A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US27851681A 1981-06-29 1981-06-29
US278,516 1981-06-29

Publications (1)

Publication Number Publication Date
CA1183286A true CA1183286A (en) 1985-02-26

Family

ID=23065276

Family Applications (1)

Application Number Title Priority Date Filing Date
CA000405436A Expired CA1183286A (en) 1981-06-29 1982-06-17 Coolant manifold for fusion reactor blanket

Country Status (5)

Country Link
JP (1) JPS587586A (en)
CA (1) CA1183286A (en)
DE (1) DE3224247A1 (en)
FR (1) FR2508590A1 (en)
GB (1) GB2100914A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4772003A (en) * 1987-02-24 1988-09-20 Dainihon Insatsu Kabushiki Kaisha Apparatus for stacking signatures or the like

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3071525A (en) * 1958-08-19 1963-01-01 Nicholas C Christofilos Method and apparatus for producing thermonuclear reactions
GB1418319A (en) * 1972-10-23 1975-12-17 Euratom Cooling system of a fusion reactor

Also Published As

Publication number Publication date
GB2100914A (en) 1983-01-06
JPS587586A (en) 1983-01-17
FR2508590A1 (en) 1982-12-31
DE3224247A1 (en) 1983-01-13

Similar Documents

Publication Publication Date Title
RU197487U1 (en) TEE NODE FOR MIXING THE FLOWS OF THE NUCLEAR REACTOR BLOWING AND SUPPLY SYSTEM
EP3301683B1 (en) A pressure-tube nuclear reactor with a low pressure moderator and fuel channel assembly
US8744035B1 (en) Reactor vessel coolant deflector shield
US10636529B2 (en) Reactor vessel reflector with integrated flow-through
JP6542224B2 (en) Heat exchanger for heat exchange between two fluids, use of said heat exchanger with liquid metal and gas and application to a liquid metal cooled fast neutron reactor
CA1064167A (en) Nuclear reactor core flow baffling
CA1183286A (en) Coolant manifold for fusion reactor blanket
US4045285A (en) Plant for the production of hydrogen through utilization of heat energy obtained from a gas-cooled nuclear reactor
US4235284A (en) Heat exchanger with auxiliary cooling system
US4120348A (en) Heat exchanger having a plurality of modules connected in parallel
KR102295616B1 (en) Concrete air cooling system using the embedded pipe
CA2622547A1 (en) Pressurized fuel channel type nuclear reactor
RU2018984C1 (en) High-temperature nuclear reactor
Holman Coolant manifold for fusion reactor blanket
GB1586480A (en) Tube bundle assembly for a heat exchanger
US5492168A (en) High convective heat transfer immersion heater/cooler
US3308878A (en) Helium heated steam generator
Sze et al. Gravity Circulated Solid Blanket Design for a Tokamak Fusion Reactor
CN104246901A (en) Feed water distributing system for a nuclear power plant, and method for operating a nuclear power plant
CN220405983U (en) Gas-loading nozzle and steam vaporization device
US4380085A (en) Angled gas conduit
JP3446855B2 (en) Sealing device for the upper shield of the HTGR and the control rod guide tube
Ihli et al. Gas-cooled divertor design approach for ARIES-CS
Guo et al. Theoretical and experimental research on the strength of distributor
Hong et al. Conceptual Design of a Small Scale High Temperature and High Pressure Gas Loop

Legal Events

Date Code Title Description
MKEC Expiry (correction)
MKEX Expiry