DE1025535B - Method for achieving a neutron flux that is equalized in the normal planes to the direction of coolant flow in thermal reactors cooled by liquid or gaseous media - Google Patents
Method for achieving a neutron flux that is equalized in the normal planes to the direction of coolant flow in thermal reactors cooled by liquid or gaseous mediaInfo
- Publication number
- DE1025535B DE1025535B DEST11579A DEST011579A DE1025535B DE 1025535 B DE1025535 B DE 1025535B DE ST11579 A DEST11579 A DE ST11579A DE ST011579 A DEST011579 A DE ST011579A DE 1025535 B DE1025535 B DE 1025535B
- Authority
- DE
- Germany
- Prior art keywords
- coolant
- reactor core
- neutron flux
- flow
- dispersion
- 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.)
- Pending
Links
- 239000002826 coolant Substances 0.000 title claims description 15
- 238000000034 method Methods 0.000 title claims description 9
- 230000004907 flux Effects 0.000 title claims description 7
- 239000007788 liquid Substances 0.000 title claims description 3
- 239000000463 material Substances 0.000 claims description 19
- 238000001816 cooling Methods 0.000 claims description 12
- 244000144987 brood Species 0.000 claims description 5
- 239000006185 dispersion Substances 0.000 claims description 5
- 238000000926 separation method Methods 0.000 claims description 3
- 238000006243 chemical reaction Methods 0.000 claims description 2
- 238000003776 cleavage reaction Methods 0.000 claims 1
- 239000000110 cooling liquid Substances 0.000 claims 1
- 230000007017 scission Effects 0.000 claims 1
- 239000000126 substance Substances 0.000 claims 1
- 238000009395 breeding Methods 0.000 description 3
- 230000001488 breeding effect Effects 0.000 description 3
- 239000000446 fuel Substances 0.000 description 2
- 241000272517 Anseriformes Species 0.000 description 1
- 210000004556 brain Anatomy 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000020169 heat generation Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 231100000572 poisoning Toxicity 0.000 description 1
- 230000000607 poisoning effect Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 239000004449 solid propellant Substances 0.000 description 1
- 239000000725 suspension Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
- G21C5/20—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone contains fissile material and another zone contains breeder material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/22—Heterogeneous reactors, i.e. in which fuel and moderator are separated using liquid or gaseous fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
- G21C5/22—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone is a superheating zone
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
Verfahren zum Erzielen eines in den Normalebenen zur Kühlmittelströmungsrichtung vergleichmäßigten Neutronenflusses in durch flüssige oder gasförmige Mittel gekühlten thermischen Reaktoren Bei Reaktoren. mit festem, makros:kopisch.en Brennstoffelem,enten. ergibt sich bei einfacher, d. h. gleich förmiger Anordnung der Brennstoffelemente im Kern und bei gleichmäßiger Konstruktion. und Anreiicherung der Elemente eine, Verteilung des, Neutronenflusses und damit der Wärmeerzeugung, die in der Kernmitte ein Maximum besitzt und nach, außen, stark abfällt. Diese; verschieden starkes Wärmeerzeugung hat zur Folge, daß auch das Tempeira,tu;rniveau über den Querschnitt ungleichmäßig verteilt ist. Man kann eine Angleichung der Temperaturen, erreichen, wenn man entsprechend dem Wärmeangebot die Kühlung stärker oder schwächer wählt und damit mehr oder weniger große Wärmemengen abführt. Günstiger ist eine, möglichst gleichmäßige, Verteilung dass Wärmeangebotes über den Kern.Method for achieving one in the normal planes to the coolant flow direction equalized neutron flux in cooled by liquid or gaseous means thermal reactors For reactors. with fixed, macros: kopisch.en fuel elements, ducks. results with simple, d. H. uniform arrangement of the fuel elements in the core and with uniform construction. and enrichment of the elements one, Distribution of the neutron flux and thus the generation of heat in the center of the core possesses a maximum and falls sharply towards the outside. These; different levels of heat generation As a result, the tempeira, door level is also uneven across the cross-section is distributed. One can achieve an equalization of the temperatures, if one accordingly the heat supply selects the cooling stronger or weaker and thus more or less dissipates large amounts of heat. A distribution that is as even as possible is more favorable that heat supply through the core.
Nach der Erfindung wird, diese; Aufgabei n.äherungsweis:e, dadurch gelöst, daß das Kühlmittel mit einer Dispersion von feinverteiltem brutfähigem Material versehen, wird, deren Konzentration in der Mitte des Reaktorkerns am, größten ist und nach außen abfällt, und zwar derart, da,ß die Konzentration in Abhängigkeit von der Lagei des, jeweiligen. Kühlkanals im Reaktorkern nach Maßgabei des sich ohne den. Zusatz dort einstellenden. mittleren. gewählt wird.According to the invention, this; Abandoning n. Approximation: e, thereby solved that the coolant with a dispersion of finely divided broodable material is provided, the concentration of which is greatest in the center of the reactor core and falls outwards in such a way that the concentration depends on of the location of the, respective. Cooling channel in the reactor core made to measure without the. Adding there setting. middle. is chosen.
Die höhere Konzentration, des, brutfähigen Materials in. der Mitte des Reaktorkerns bewirkt dort einen größeren Neutroneneinfang als in den Randgebieiten des Realctorkeirns. Dadurch wird der N.eutronenfluß in der Kernmittei stärker herabgesetzt als am Rand, so. daß beide, einander angeglichen werden. Man kann somit einen, angenähert gleichmäßigen NeutronEnfluß in Normalebenen, zur Strömungsrichtung des Kühlmittels und damit eine Vergleichmäßigung der Wärmeientwicklung über den Querschnitt des Reiaktors eirreichen, wenn man die! Konzentration, des brutfähigen Materials als Funktion der Entfernung von der parallel zur Strömungsrichtung liegenden Mittelachse: dies Reaktors nach Maßgabe, des mittleren Neutronenflussies im jeweiligen Kühilkanal ohne Zusatz wählt.The higher concentration of the material that can be brood in the middle of the reactor core causes greater neutron capture there than in the peripheral areas of the realctor's brain. As a result, the neutron flux in the core is reduced more than on the edge, so. that both are assimilated to one another. One can thus approximate one Uniform neutron flow in normal planes to the direction of flow of the coolant and thus an equalization of the heat development over the cross-section of the Reiactor's reach if you can! Concentration, of the material capable of breeding as Function of the distance from the central axis parallel to the direction of flow: this reactor according to the mean neutron flux in the respective cooling channel dials without addition.
Einerz weiteren Gedanken, der Erfindung entsprechend soll dies dadurch, realisiert werden, d.aß das. Kühlmitteil vor seinem. Eintritt in die Kühlkanäle Abs:cheidevorrichtungen an sieh bekannter Art durchläuft, die in. ihrem Abscheidewirkungsgrad bei den mittleren Kanälen am niedrigsten liegen und bei den äußerem, am, höchsten.Another idea, according to the invention, is to do this by be realized, i.e. the. cooling part before his. Entry into the cooling channels Abs: separating devices of a known type passes through, which in their separation efficiency lowest in the middle canals and highest in the outer canals.
Das abgeschiedenes Brutmaterial kann durch. eine paralleil geschaltete Strömung in ein ringförmiges Hüllgebiet um den Reaktorkern geleitet werden und sich im Anschluß daran mit den aus dem Reiaktockern kommenden Strömen wiedervereinigen. Gleichzeitig wird durch eine solche Anordnung erreicht, daß bei wachsendem Kühlmittelstrom und damit wachsender Küh;lmttelgesch.windigkeit ganz allgemein die Konzentration an brutfähigere Material im Reaktorkern sinkt, so daß mehr Wärme frei wird, die durch die größere Menge des Kühlmaterials abgeführt werden kann.. Umgekehrt würde: bei Verringerung der Kühlmittelmenge auch die; erzeugte Wärmemenge sinken. Im Extremfall kann, dafür gesorgt sein, daß bei Ausfall dass Kühlmittel.stroms die Kühlkanäle im Reaktorkern, sich. so weit mit dem brutfähigen, Material füllen, daß die Reaktion selbsttätig eirlisch.t.The deposited brood material can pass through. one connected in parallel Flow in an annular enveloping area around the reactor core and are directed then reunite with the streams coming from the Reiaktockern. At the same time it is achieved by such an arrangement that with increasing coolant flow and with it increasing cooling speed, concentration in general sinks of more fertile material in the reactor core, so that more heat is released can be removed by the larger amount of the cooling material .. The reverse would be: when reducing the amount of coolant also the; The amount of heat generated will decrease. In the extreme it can be ensured that, in the event of a failure, the coolant flow through the cooling channels in the reactor core, yourself. Fill so far with the breeding material that the reaction automatically eirlisch.t.
Durch die Verwendung von suspendiertem brutfähigem Material im Kühlmittel ist außerdem. die Möglichkeit einer kontinuierlichen Aufbereitung gegeben. Es kann laufend ausgebrütetes Material bzw. Material der Zwischenstufen aus dem Kreislauf entfeirnt und andererseits zur Erhöhung der Reaktivität, beispielsweise bei Erschöpfung oder weitgehender Vergiftung der festen Brennstoffeilemente, zusätzlich spaltbares Material in Suspension gegeben werden. Dies bedeutet wiederum, d.aß eine kontinuierliche Aufbereitung vorgesehen wird, weilche die entstehenden Spaltprod uktei entfernt.By using suspended breeding material in the coolant is also. given the possibility of continuous processing. It can continuously hatched material or material of the intermediate stages from the cycle removed and on the other hand to increase the reactivity, for example when exhausted or extensive poisoning of the solid fuel elements, additionally fissile Material to be given in suspension. This in turn means that a continuous Processing is provided because the resulting fission products are removed.
Claims (7)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DEST11579A DE1025535B (en) | 1956-08-24 | 1956-08-24 | Method for achieving a neutron flux that is equalized in the normal planes to the direction of coolant flow in thermal reactors cooled by liquid or gaseous media |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DEST11579A DE1025535B (en) | 1956-08-24 | 1956-08-24 | Method for achieving a neutron flux that is equalized in the normal planes to the direction of coolant flow in thermal reactors cooled by liquid or gaseous media |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE1025535B true DE1025535B (en) | 1958-03-06 |
Family
ID=7455445
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEST11579A Pending DE1025535B (en) | 1956-08-24 | 1956-08-24 | Method for achieving a neutron flux that is equalized in the normal planes to the direction of coolant flow in thermal reactors cooled by liquid or gaseous media |
Country Status (1)
| Country | Link |
|---|---|
| DE (1) | DE1025535B (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1146987B (en) * | 1960-04-04 | 1963-04-11 | Babcock & Wilcox Dampfkessel | Neutron absorbing agent for regulating the reactivity of nuclear reactors |
| DE1191049B (en) * | 1961-03-04 | 1965-04-15 | Bbc Brown Boveri & Cie | Process for achieving a uniform power density in gas-cooled pebble bed high-temperature nuclear reactors |
-
1956
- 1956-08-24 DE DEST11579A patent/DE1025535B/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1146987B (en) * | 1960-04-04 | 1963-04-11 | Babcock & Wilcox Dampfkessel | Neutron absorbing agent for regulating the reactivity of nuclear reactors |
| DE1191049B (en) * | 1961-03-04 | 1965-04-15 | Bbc Brown Boveri & Cie | Process for achieving a uniform power density in gas-cooled pebble bed high-temperature nuclear reactors |
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