GB1595120A - Heat exchanger - Google Patents
Heat exchanger Download PDFInfo
- Publication number
- GB1595120A GB1595120A GB23629/78A GB2362978A GB1595120A GB 1595120 A GB1595120 A GB 1595120A GB 23629/78 A GB23629/78 A GB 23629/78A GB 2362978 A GB2362978 A GB 2362978A GB 1595120 A GB1595120 A GB 1595120A
- Authority
- GB
- United Kingdom
- Prior art keywords
- vessel
- tube
- heat exchanger
- exchanger according
- pressure relief
- 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
Links
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims description 12
- 229910052708 sodium Inorganic materials 0.000 claims description 12
- 239000011734 sodium Substances 0.000 claims description 12
- 238000005192 partition Methods 0.000 claims description 8
- 238000009434 installation Methods 0.000 claims description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 7
- 238000004891 communication Methods 0.000 claims description 6
- 239000012530 fluid Substances 0.000 claims description 6
- 239000007788 liquid Substances 0.000 claims description 6
- 238000000034 method Methods 0.000 claims description 3
- 238000012806 monitoring device Methods 0.000 claims description 3
- 230000010355 oscillation Effects 0.000 claims description 3
- 238000001514 detection method Methods 0.000 claims description 2
- 238000000605 extraction Methods 0.000 claims description 2
- 239000011261 inert gas Substances 0.000 claims description 2
- 238000012360 testing method Methods 0.000 claims description 2
- 238000002604 ultrasonography Methods 0.000 claims description 2
- 239000000523 sample Substances 0.000 description 5
- 239000002826 coolant Substances 0.000 description 4
- 238000012544 monitoring process Methods 0.000 description 3
- 239000007795 chemical reaction product Substances 0.000 description 2
- NASFKTWZWDYFER-UHFFFAOYSA-N sodium;hydrate Chemical compound O.[Na] NASFKTWZWDYFER-UHFFFAOYSA-N 0.000 description 2
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/06—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
- F22B1/063—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
(54) HEAT EXCHANGER
(71) We, INTERATOM, INTERNA
TIONALE ATOMREAKTORBAU
GmbH, a German company of Bergisch
Gladbach 1, Germany, do hereby declare the invention, for which we pray that a patent may be granted to us, and the method by which it is to be performed, to be particularly described in and by the following statement: This invention relates to a heat exchanger.
According to the present invention, there is provided a heat exchanger comprising:
a) a vessel for containing a first exchange medium;
b) at least one bundle of tubes within the vessel for containing a second exchange medium; and
c) a pressure relief and instrumentation tube also within the vessel, which tube is normally closed off from the interior of the vessel and is capable of being withdrawn from the vessel to enable the interior of the vessel to be inspected, but which does not contain a tube bundle.
In order that the present invention may be more fully understood, an embodiment of heat exchanger according to the present invention will be described, by way of example, with reference to the accompanying drawing, in which:
Figure 1 is a vertical longitudinal section through the heat exchanger, taken along the line I-I in Figure 2; and
Figure 2 is a horizontal cross-section through the heat exchanger, taken along the line 11-Il in Figure 1.
A heat exchanger or steam generator vessel containing a plurality of vertical, upwardly extractable tube bundles may be required to be capable of being used with at least one corrosive medium, such as liquid
metal or various organic substances having low pressures and/or good thermal properties at high temperatures, but which, on contact with the oxygen of the air with water, may react extremely violently. These
media must therefore be very carefully enclosed. Possible lack of fluid-tightness or cases of damage in such vessels are, therefore, to be as far as possible prevented.
Thus, it is particularly desirable that such vessels and the tube bundles therein should be capable of being tested at regular intervals and with the least possible expenditure of time.
In Specification No. 1,514,831, there is proposed a liquid metaVwater heat exchanger, wherein a plurality of vertical tube bundles are arranged in a vessel in such a manner as to be removable therefrom.
Each of the tube bundles has at its centre a central tube in which are contained inter alia downwardly extending feed water pipes and in which there may be arranged leakage or oscillation monitoring probes. The provision of monitoring probes in each individual tube bundle is naturally associated with considerable outlay and each probe can be employed only for monitoring the tube bundle with which it is accociated. If the vessel itself is to be monitored or inspected, it is necessary either to provide supplementary probes or to remove one or more of the tube bundles in order.that the vessel may be inspected from the interior.
The embodiment of heat exchanger according to the present invention shown in
Figures 1 and 2 is a liquid sodium/water heat exchanger for a sodium-cooled nuclear reactor installation. The exchanger comprises a cylindrical vessel I having circular cross-section for containing liquid sodium as the first exchange medium sealed at its upper end with a rounded lid 2 and having a rounded end wall 3 at it slower end.
A horizontal intermediate partition 4 is provided towards the upper end of the vessel I and a horizontal intermediate partition 5 is provided towards the lower end of the vessel 1. These horizontal intermediate partitions 4 and 5 are formed with a plurality of cylindrical apertures extending therethrough in which there are inserted sligingly but almost in fluid-tight manner a plurality of tube bundles 6 for containing water-steam as the second exchange medium, a pressure relief and instrumentation tube 7 and a pump housing 8. The tube 7 is closed off from the interior of the vessel and is capable of being withdrawn from the vessel to enable the interior of the vessel to be inspected, but does not contain a tube bundle.As shown only with respect to one of the tube bundles 6 n Figure 1, all these parts 6, 7, 6r are welded in fluidtight manner to the lid 2 such that the weld seam can, with only slight expenditure, be opened up and subsequently closed again by welding. Thus the vessel 1 is absolute, fluid-tight, but the various parts 6, 7, 8 can nevertheless be released and moved upwardly out of the vessel 1 with only a slight outlay. The tube 7 is of substantially smaller diameter than the tube bundles 6 and can therefore be more readily extracted from the vessel 1 for purposes of inspection.
The tube 7 extends along the axis of the vessel and each tube bundle extends parallel to the axis of the vessel, as does the pump housing 8.
Arranged in the tubular wall of the tube 7, respectively in the vicinity of the end wall 3 and in the vicinity of the lid 2, there is in each case at least one rupture or safety disc 16 which, in the event of damage, for example in the event of a pressure increase due to a sodium-water reaction occurring as a result of damage to the tubes of the tube bundles 6, rapidly and reliably releases a large cross-section and conveys a mixture of sodium and various reaction products initially to a separator (not shown) which separates the reaction products and then to a relief vessel (also not shown). In the event of such a sodium-water reaction, the path from the location of damage to a disc 16 should be as short as possible, in order that the rupture disc may be able to respond rapidly.Due to the arrangement of the discs 16 in the retractable tube 7, the discs 16 can be tested or replaced with only slight outlay and it is not necessary to provide special apertures or pipelines on the vessel for this purpose. Additionally, by attachment of suitable probes, the discs 16 can be monitored electrically. A suitable monitoring device for this purpose is disclosed in British Patent Specification No.
1,374,296. The discs 16 are useful mainly in sodium/water heat exchangers, such as that illustrated, but can also be employed in sodium/sodium heat exchangers for protection of the vessel 1 in the event of power excursions of the reactor.
In operation of the heat exchanger illustrated, the primary coolant constituted by liquid sodium flows through an inlet 9 into a first chamber between the upper intermediate partition 4 and the lid 2, and from there through lateral apertures in casings of the tube bundles 6 and downwardly within the casings and through further lateral apertures into a second chamber between the lower intermediate portion 5 and the end wall 3. From there it is sucked into the pump housing 8 via a pump inlet 11 and expelled into a third chamber between the two intermediate partitions 4 and 5, from where it flows between the inner wall of the vessel 1 and guiding means in the form of a cylindrical wall 12 secured to the upper intermediate partition 4 to an outlet
10.The purpose of the cylindrical wall 12 is to ensure that the temperature of the inner wall of the vessel 1 in the vicinity of the wall
12 continuously corresponds to the outflow temperature of the sodium (which is less than the inflow temperature), so that the thermal loading of the vessel 1 is minimised.
The secondary coolant, which in the case
of the illustrated embodiment is water/steam but which may also be sodium, enters the tube bundles 6 at their upper
ends and flows through vertical down tubes
13 to the lower ends of the tube bundles 6
where it reverses its direction of flow and
flows through a plurality of thin-walled
tubes 14 back to the upper ends of the tube
bundles 6 and out through an outlet 15. In
the course of flowing through the tubes 14
the secondary coolant is heated by the
primary coolant flowing between the
outsides of the tubes 14 and the casings.
Figure 2 in particular shows how the tube
bundles 6, the pressure relief and instrumentation tube 7 and the pump housing 8 are arranged in space-saving manner in the cylindrical vessel 1 so that the heat exchanger is particularly compact. Due to the eccentric arrangement of the pump housing 8 and due to the arrangement of the tube 7 (having a diameter very much smaller than that of the tube bundles 6) substantially in the centre of the vessel 1, the number of tube bundles which are to be provided and their diameter can be chosen almost at will without wasting space. The eccentric arrangement does not lead to substantially
non-uniform temperatures about the
periphery of the vessel and to resultant
peripheral stressing of the vessel since the
major portions of the tube bundle casings
and the pump housings 8 are surrounded
only by a medium which has already
discharged its heat to the tube bundles. The
eccentric arrangement of the pump housing 8 which has a substantially larger diameter than the tube 7 affords an extremely spacesaving arrangement.
Instrumentation 17 is disposed in the tube 7 so as to be accessible for maintenance.
Such instrumentation 17 may comprise, for example, devices for detecting boiling noises in the sodium and providing a warning of approaching damage to the tube bundles and/or leakage detection devices and/or oscillation metering devices and/or temperature metering devices. The tube 7 may be removed and replaced by an observation or manipulator tube in cases of damage so that the instrumentation can be tested after extraction of the tube 7. In the case of a sodium-cooled nuclear reactor installation, the tube 7 can be pulled into an exchange tank which is sealed on all sides and is filled with an inert gas, so that the extracted tube 7 does not come into contact with the atmosphere. The tube bundles 6 can be treated in the same manner.
The heat exchanger described above with reference to the drawing is particularly advantageous since it may be employed with corrosive media and since the tube bundles may be extracted from the vessel.
Furthermore the heat exchanger is capable of being tested from the interior of the vessel with the minimal outlay and minimal expenditure of time. Also the wall of the vessel is provided with only a small number of welded connections which prejudice rigidity of the vessel and make testing with the known ultrasound and eddy current processes more difficult.
WHAT WE CLAIM IS:
1. A heat exchanger comprising:
a) a vessel for containing a first exchange medium;
b) at least one bundle of tubes within the vessel for containing a second exchange medium; and
c) a pressure relief and instrumentation tube also within the vessel, which tube is normally closed off from the interior of the vessel and is capable of being withdrawn from the vessel to enable the interior of the vessel to be inspected, but which does not contain a tube bundle.
2. A heat exchanger according to claim 1 wherein the vessel is substantially cylindrical and has a circular cross-section and the pressure relief and instrumentation tube extends along the axis of the vessel.
3. A heat exchanger according to claim 2, wherein the or each tube bundle is elongate and extends parallel to the axis of the vessel.
4. A heat exchanger according to claim 3, wherein the pressure relief and instrumentation tube and the tube bundle(s) are connected to the vessel in such a manner that they may be withdrawn from the vessel parallel to their lengths.
5. A heat exchanger according to claim 4, wherein the pressure relief and instrumentation tube is suspended from one end of the vessel.
6. A heat exchanger according to any preceding claim, wherein the pressure relief and instrumentation tube has one or more rupture discs disposed in its tubular wall, the rupture disc(s) being adapted to be ruptured when an excess pressure prevails in the vessel.
7. A heat exchanger according to any preceding claim, wherein the pressure relief and instrumentation tube is adapted to be connected to a separator and/or a relief vessel.
8. A heat exchanger according to any preceding claim, wherein the vessel also contains a pump connected to the vessel in such a manner that it may be withdrawn from the vessel.
9. A heat exchanger according to claim 8 8 when appended directly or indirectly to claim 2, wherein the pump is elongate and extends parallel to the axis of the vessel.
10. A heat exchanger according to any preceding claim, wherein the or each bundle is contained within a tubular casing having at least one opening at each end region.
11. A heat exchanger according to claim 10 when appended to claim 8 or 9, wherein the interior of the vessel is divided into three chambers by two partitions, a first of the chambers being in fluid communication with an inlet of the vessel and the opening(s) at one end of the or each tube bundle, a second of the chambers being in fluid communication with the opening(s) at the other end of the or each tube bundle and an inlet of the pump, and a third of the chambers intermediate the first and second chambers being in fluid communication with an outlet of the pump and an outlet of the vessel.
12. A heat exchanger according to claim 11, wherein means are provided for guiding the flow of first exchange medium towards the outlet of the vessel by way of a region adjacent a wall of the vessel.
13. A heat exchanger according to claim 8, 9, 11 or 12 or claim 10 when appended to claim 8 or 9, wherein the tube bundle(s), the pressure relief and instrumentation tube and the pump are suspended from a lid of the vessel.
14. A heat exchanger according to any preceding claim, wherein the pressure relief and instrumentation tube contains at least one monitoring device.
15. A heat exchanger substantially as hereinbefore described with reference to, and/or as illustrated in, the accompanying drawing.
16. A nuclear reactor installation incorporating a heat exchanger according to ahy preceding claim.
17. An installation according to claim 16, adapted to be operated with liquid sodium as the first exchange medium and water/steam as the second exchange medium.
**WARNING** end of DESC field may overlap start of CLMS **.
Claims (18)
1. A heat exchanger comprising:
a) a vessel for containing a first exchange medium;
b) at least one bundle of tubes within the vessel for containing a second exchange medium; and
c) a pressure relief and instrumentation tube also within the vessel, which tube is normally closed off from the interior of the vessel and is capable of being withdrawn from the vessel to enable the interior of the vessel to be inspected, but which does not contain a tube bundle.
2. A heat exchanger according to claim 1 wherein the vessel is substantially cylindrical and has a circular cross-section and the pressure relief and instrumentation tube extends along the axis of the vessel.
3. A heat exchanger according to claim 2, wherein the or each tube bundle is elongate and extends parallel to the axis of the vessel.
4. A heat exchanger according to claim 3, wherein the pressure relief and instrumentation tube and the tube bundle(s) are connected to the vessel in such a manner that they may be withdrawn from the vessel parallel to their lengths.
5. A heat exchanger according to claim 4, wherein the pressure relief and instrumentation tube is suspended from one end of the vessel.
6. A heat exchanger according to any preceding claim, wherein the pressure relief and instrumentation tube has one or more rupture discs disposed in its tubular wall, the rupture disc(s) being adapted to be ruptured when an excess pressure prevails in the vessel.
7. A heat exchanger according to any preceding claim, wherein the pressure relief and instrumentation tube is adapted to be connected to a separator and/or a relief vessel.
8. A heat exchanger according to any preceding claim, wherein the vessel also contains a pump connected to the vessel in such a manner that it may be withdrawn from the vessel.
9. A heat exchanger according to claim 8 8 when appended directly or indirectly to claim 2, wherein the pump is elongate and extends parallel to the axis of the vessel.
10. A heat exchanger according to any preceding claim, wherein the or each bundle is contained within a tubular casing having at least one opening at each end region.
11. A heat exchanger according to claim 10 when appended to claim 8 or 9, wherein the interior of the vessel is divided into three chambers by two partitions, a first of the chambers being in fluid communication with an inlet of the vessel and the opening(s) at one end of the or each tube bundle, a second of the chambers being in fluid communication with the opening(s) at the other end of the or each tube bundle and an inlet of the pump, and a third of the chambers intermediate the first and second chambers being in fluid communication with an outlet of the pump and an outlet of the vessel.
12. A heat exchanger according to claim 11, wherein means are provided for guiding the flow of first exchange medium towards the outlet of the vessel by way of a region adjacent a wall of the vessel.
13. A heat exchanger according to claim 8, 9, 11 or 12 or claim 10 when appended to claim 8 or 9, wherein the tube bundle(s), the pressure relief and instrumentation tube and the pump are suspended from a lid of the vessel.
14. A heat exchanger according to any preceding claim, wherein the pressure relief and instrumentation tube contains at least one monitoring device.
15. A heat exchanger substantially as hereinbefore described with reference to, and/or as illustrated in, the accompanying drawing.
16. A nuclear reactor installation incorporating a heat exchanger according to ahy preceding claim.
17. An installation according to claim 16, adapted to be operated with liquid sodium as the first exchange medium and water/steam as the second exchange medium.
18. A compact heat exchanger or steam
generator vessel for corrosive media,
containing a plurality of perpendicular heat exchanger or steam generator tube bundles adapted to be extracted from above, and, apart from the tube bundles, a central pressure relief and instrumentation tube which is sealed below and adapted to be extracted upwardly.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19772725877 DE2725877A1 (en) | 1977-06-08 | 1977-06-08 | HEAT EXCHANGER FOR AGGRESSIVE MEDIA |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1595120A true GB1595120A (en) | 1981-08-05 |
Family
ID=6011054
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB23629/78A Expired GB1595120A (en) | 1977-06-08 | 1978-05-26 | Heat exchanger |
Country Status (4)
Country | Link |
---|---|
DE (1) | DE2725877A1 (en) |
FR (1) | FR2394051A1 (en) |
GB (1) | GB1595120A (en) |
NL (1) | NL7805595A (en) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2483592A1 (en) * | 1980-06-02 | 1981-12-04 | Stein Industrie | DEVICE FOR REDUCING THERMAL CONSTRAINTS ON A HEAT EXCHANGER |
JPS58158498A (en) * | 1982-03-15 | 1983-09-20 | Hitachi Ltd | Heat exchanger |
FR2544053B1 (en) * | 1983-04-07 | 1985-06-28 | Commissariat Energie Atomique | STEAM GENERATOR FOR A LIQUID METAL COOLED REACTOR |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3613780A (en) * | 1968-09-25 | 1971-10-19 | Sergio Bruschetti | Liquid metal heat exchangers with pressure absorbing means |
US3741167A (en) * | 1971-03-02 | 1973-06-26 | Foster Wheeler Corp | Sodium heated steam generator |
FR2300963A1 (en) * | 1975-02-12 | 1976-09-10 | Commissariat Energie Atomique | STEAM GENERATOR |
-
1977
- 1977-06-08 DE DE19772725877 patent/DE2725877A1/en not_active Withdrawn
-
1978
- 1978-05-23 NL NL7805595A patent/NL7805595A/en not_active Application Discontinuation
- 1978-05-26 GB GB23629/78A patent/GB1595120A/en not_active Expired
- 1978-06-07 FR FR787817092A patent/FR2394051A1/en not_active Withdrawn
Also Published As
Publication number | Publication date |
---|---|
FR2394051A1 (en) | 1979-01-05 |
NL7805595A (en) | 1978-12-12 |
DE2725877A1 (en) | 1978-12-21 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB1584922A (en) | Heat exchanger/pump assembly | |
KR101038399B1 (en) | Steam generator for the sodium cooled fast reactor with an on-line leak detection system | |
US4273076A (en) | Steam generator sludge lancing apparatus | |
US20070201608A1 (en) | Method for testing a fuel rod cladding tube and associated device | |
US3098023A (en) | Nuclear reactor containment system | |
US4079967A (en) | Industrial technique | |
CA1080691A (en) | Helical coil steam generator | |
JPS61262501A (en) | Double pipe helical coil type steam generator | |
JP4101422B2 (en) | Liquid metal cooled nuclear reactor and liquid metal cooled nuclear power plant | |
CN105551542A (en) | Water-cooling containment simulation device | |
JPS62158901A (en) | Double tube type steam generator | |
GB1595120A (en) | Heat exchanger | |
US3741167A (en) | Sodium heated steam generator | |
US3497421A (en) | Shielded enclosure providing resistance to high temperatures and pressures | |
KR100936551B1 (en) | Apparatus and method for repairing reactor vessel cladding using a seal plate | |
JPH1062590A (en) | Recovering device of fluid contained in coolant circuit of reactor | |
US3668069A (en) | Pressure suppression containment for a liquid-cooled nuclear reactor | |
US3908756A (en) | Tube-in-shell heat exchangers | |
CN106531241B (en) | Double-walled heat exchanger tube and liquid-metal reactor double-wall pipe heat transmission equipment | |
US4515748A (en) | Apparatus for detection of losses in a vapor generator | |
JPS59157401A (en) | Steam generator for liquid metal cooling type nuclear reactor | |
KR100558513B1 (en) | Leak detection device for once-through steam generator by using of gas circulation | |
CN114743698B (en) | Succinct high temperature gas cooled reactor waste heat discharge system | |
Saez et al. | Sodium-Water Reaction approach and mastering for ASTRID Steam Generator design | |
CN206092941U (en) | Pressure container |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PCNP | Patent ceased through non-payment of renewal fee |