METHOD AND REACTOR FOR THE GENERATION OF ENERGY IN THE PROCESS OF A CONTROLLED NUCLEAR FISSION
In a known method for the generation of energy in the process of a controlled nuclear fission by means of neutrons, the improvements reside in that it comprises selection and a directed recovery of thermal neutrons into a thermal neutron region of the fissile core, circulation of a fuel composition...
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| description | In a known method for the generation of energy in the process of a controlled nuclear fission by means of neutrons, the improvements reside in that it comprises selection and a directed recovery of thermal neutrons into a thermal neutron region of the fissile core, circulation of a fuel composition is performed over two loops one of which passing through the thermal neutron region and a cooling region and the other passing through the fast neutron region and the cooling region, and a material of fuel compositions of both loops is interchanged. The fuel composition is disposed within at least two loops one of which intersecting the thermal neutron region and the other intersecting the fast neutron region of the fissile core, and said loops are interconnected by a device for interchanging a material of both loops, said moderator is made in the form of a hollow shaper of a directed thermal neutron flux, said fissile core is located in a hollow, and said shaper comprises ducts for shaping a directed neutron flux oriented only in the direction of a fuel composition loop intersecting the thermal neutron region of the fissile core.
Procédé pour la production d'énergie par fission nucléaire contrôlée à l'aide de neutrons, ce procédé étant perfectionné en ce qu'il comporte une sélection et une récupération orientée des neutrons thermiques dans une zone à neutrons thermiques du noyau fissile. On met en circulation une composition combustible dans deux boucles dont l'une traverse la zone à neutrons thermiques et une zone de refroidissement, tandis que l'autre traverse la zone à neutrons rapides et la zone de refroidissement, et on échange une matière des compositions combustibles des deux boucles. La composition combustible se situe à l'intérieur d'au moins deux boucles dont l'une croise la zone à neutrons thermiques tandis que l'autre croise la zone à neutrons rapides du noyau fissile, et ces boucles sont reliées entre elles par un dispositif d'échange d'une matière des deux boucles. Le modérateur se présente sous la forme d'un dispositif creux pour la mise en forme d'un flux orienté de neutrons thermiques, le noyau fissile se situe dans un creux, et ledit dispositif de mise en forme comporte des conduits qui n'assurent la mise en forme d'un flux orienté de neutrons qu'en direction d'une boucle à composition combustible croisant la zone à neutrons thermiques du noyau fissile. |
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Procédé pour la production d'énergie par fission nucléaire contrôlée à l'aide de neutrons, ce procédé étant perfectionné en ce qu'il comporte une sélection et une récupération orientée des neutrons thermiques dans une zone à neutrons thermiques du noyau fissile. On met en circulation une composition combustible dans deux boucles dont l'une traverse la zone à neutrons thermiques et une zone de refroidissement, tandis que l'autre traverse la zone à neutrons rapides et la zone de refroidissement, et on échange une matière des compositions combustibles des deux boucles. La composition combustible se situe à l'intérieur d'au moins deux boucles dont l'une croise la zone à neutrons thermiques tandis que l'autre croise la zone à neutrons rapides du noyau fissile, et ces boucles sont reliées entre elles par un dispositif d'échange d'une matière des deux boucles. Le modérateur se présente sous la forme d'un dispositif creux pour la mise en forme d'un flux orienté de neutrons thermiques, le noyau fissile se situe dans un creux, et ledit dispositif de mise en forme comporte des conduits qui n'assurent la mise en forme d'un flux orienté de neutrons qu'en direction d'une boucle à composition combustible croisant la zone à neutrons thermiques du noyau fissile.</description><edition>6</edition><language>eng ; fre</language><subject>GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC ; GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS ; NUCLEAR ENGINEERING ; NUCLEAR PHYSICS ; NUCLEAR REACTORS ; PHYSICS ; REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGYGENERATION, TRANSMISSION OR DISTRIBUTION ; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS ; TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE</subject><creationdate>1997</creationdate><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://worldwide.espacenet.com/publicationDetails/biblio?FT=D&date=19970904&DB=EPODOC&CC=WO&NR=9732313A1$$EHTML$$P50$$Gepo$$Hfree_for_read</linktohtml><link.rule.ids>230,309,781,886,25569,76552</link.rule.ids><linktorsrc>$$Uhttps://worldwide.espacenet.com/publicationDetails/biblio?FT=D&date=19970904&DB=EPODOC&CC=WO&NR=9732313A1$$EView_record_in_European_Patent_Office$$FView_record_in_$$GEuropean_Patent_Office$$Hfree_for_read</linktorsrc></links><search><creatorcontrib>DROBYSHEVSKY, JURY VASILIEVICH</creatorcontrib><creatorcontrib>STOLBOV, SERGEI NIKOLAEVICH</creatorcontrib><title>METHOD AND REACTOR FOR THE GENERATION OF ENERGY IN THE PROCESS OF A CONTROLLED NUCLEAR FISSION</title><description>In a known method for the generation of energy in the process of a controlled nuclear fission by means of neutrons, the improvements reside in that it comprises selection and a directed recovery of thermal neutrons into a thermal neutron region of the fissile core, circulation of a fuel composition is performed over two loops one of which passing through the thermal neutron region and a cooling region and the other passing through the fast neutron region and the cooling region, and a material of fuel compositions of both loops is interchanged. The fuel composition is disposed within at least two loops one of which intersecting the thermal neutron region and the other intersecting the fast neutron region of the fissile core, and said loops are interconnected by a device for interchanging a material of both loops, said moderator is made in the form of a hollow shaper of a directed thermal neutron flux, said fissile core is located in a hollow, and said shaper comprises ducts for shaping a directed neutron flux oriented only in the direction of a fuel composition loop intersecting the thermal neutron region of the fissile core.
Procédé pour la production d'énergie par fission nucléaire contrôlée à l'aide de neutrons, ce procédé étant perfectionné en ce qu'il comporte une sélection et une récupération orientée des neutrons thermiques dans une zone à neutrons thermiques du noyau fissile. On met en circulation une composition combustible dans deux boucles dont l'une traverse la zone à neutrons thermiques et une zone de refroidissement, tandis que l'autre traverse la zone à neutrons rapides et la zone de refroidissement, et on échange une matière des compositions combustibles des deux boucles. La composition combustible se situe à l'intérieur d'au moins deux boucles dont l'une croise la zone à neutrons thermiques tandis que l'autre croise la zone à neutrons rapides du noyau fissile, et ces boucles sont reliées entre elles par un dispositif d'échange d'une matière des deux boucles. 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The fuel composition is disposed within at least two loops one of which intersecting the thermal neutron region and the other intersecting the fast neutron region of the fissile core, and said loops are interconnected by a device for interchanging a material of both loops, said moderator is made in the form of a hollow shaper of a directed thermal neutron flux, said fissile core is located in a hollow, and said shaper comprises ducts for shaping a directed neutron flux oriented only in the direction of a fuel composition loop intersecting the thermal neutron region of the fissile core.
Procédé pour la production d'énergie par fission nucléaire contrôlée à l'aide de neutrons, ce procédé étant perfectionné en ce qu'il comporte une sélection et une récupération orientée des neutrons thermiques dans une zone à neutrons thermiques du noyau fissile. On met en circulation une composition combustible dans deux boucles dont l'une traverse la zone à neutrons thermiques et une zone de refroidissement, tandis que l'autre traverse la zone à neutrons rapides et la zone de refroidissement, et on échange une matière des compositions combustibles des deux boucles. La composition combustible se situe à l'intérieur d'au moins deux boucles dont l'une croise la zone à neutrons thermiques tandis que l'autre croise la zone à neutrons rapides du noyau fissile, et ces boucles sont reliées entre elles par un dispositif d'échange d'une matière des deux boucles. Le modérateur se présente sous la forme d'un dispositif creux pour la mise en forme d'un flux orienté de neutrons thermiques, le noyau fissile se situe dans un creux, et ledit dispositif de mise en forme comporte des conduits qui n'assurent la mise en forme d'un flux orienté de neutrons qu'en direction d'une boucle à composition combustible croisant la zone à neutrons thermiques du noyau fissile.</abstract><edition>6</edition><oa>free_for_read</oa></addata></record> |
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| subjects | GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS NUCLEAR ENGINEERING NUCLEAR PHYSICS NUCLEAR REACTORS PHYSICS REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGYGENERATION, TRANSMISSION OR DISTRIBUTION TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE |
| title | METHOD AND REACTOR FOR THE GENERATION OF ENERGY IN THE PROCESS OF A CONTROLLED NUCLEAR FISSION |
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