Heat pipe networks for heat removal, such as heat removal from nuclear reactors, and associated systems and methods
US-2023317306-A1 · Oct 5, 2023 · US
US2020194132A1 · US · A1
| Field | Value |
|---|---|
| Publication number | US-2020194132-A1 |
| Application number | US-201916691038-A |
| Country | US |
| Kind code | A1 |
| Filing date | Nov 21, 2019 |
| Priority date | Dec 17, 2018 |
| Publication date | Jun 18, 2020 |
| Grant date | — |
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When all fuel assemblies loaded in a region excluding an outermost periphery of the reactor core in an Nth operation cycle belong to the first fuel assembly, and all fuel assemblies loaded in the region excluding the outermost periphery of the reactor core in a (N+m) th (m>1) operation cycle belong to the second fuel assembly, the number of new loaded second fuel assemblies in the (N+m) th operation cycle is greater than the number of new loaded second fuel assemblies in a (N+m−1) th operation cycle which is one operation cycle before the (N+m) th operation cycle, and a cycle burnup in the (N+m) th operation cycle is greater than a cycle burnup in the (N+m−1) th operation cycle.
Opening claim text (preview).
1 . A fuel loading method for a transition reactor core when transitioning from a first fuel assembly to a second fuel assembly in which at least one of an average uranium enrichment, an average fissile plutonium enrichment, and a fuel rod arrangement is different from that of the first fuel assembly, wherein when all fuel assemblies loaded in a region excluding an outermost periphery of the reactor core in an Nth operation cycle belong to the first fuel assembly, and all fuel assemblies loaded in the region excluding the outermost periphery of the reactor core in a (N+m)th (m>1) operation cycle belong to the second fuel assembly, the number of new loaded second fuel assemblies in the (N+m) th operation cycle is greater than the number of new loaded second fuel assemblies in a (N+m−1)th operation cycle which is one operation cycle before the (N+m)th operation cycle, and a cycle burnup in the (N+m)th operation cycle is greater than a cycle burnup in the (N+m−1)th operation cycle. 2 . The fuel loading method according to claim 1 , wherein all the fuel assemblies in the reactor core in the Nth operation cycle belong to the first fuel assembly, and all the fuel assemblies in the reactor core in the (N+m) th operation cycle belong to the second fuel assembly. 3 . The fuel loading method according to claim 1 , wherein the first fuel assembly is a square grid fuel rod array of 9 rows and 9 columns, and the second fuel assembly is a square grid fuel rod array of 10 rows and 10 columns. 4 . The fuel loading method according to claim 2 , wherein the first fuel assembly is a square grid fuel rod array of 9 rows and 9 columns, and the second fuel assembly is a square grid fuel rod array of 10 rows and 10 columns. 5 . The fuel loading method according to claim 1 , wherein the first fuel assembly is a square grid fuel rod array of 10 rows and 10 columns, and the second fuel assembly is a square grid fuel rod array of 11 rows and 11 columns. 6 . The fuel loading method according to claim 2 , wherein the first fuel assembly is a square grid fuel rod array of 10 rows and 10 columns, and the second fuel assembly is a square grid fuel rod array of 11 rows and 11 columns. 7 . The fuel loading method according to claim 1 , wherein the average uranium enrichment of the second fuel assembly is higher than the average uranium enrichment of the first fuel assembly. 8 . The fuel loading method according to claim 2 , wherein the average uranium enrichment of the second fuel assembly is higher than the average uranium enrichment of the first fuel assembly. 9 . The fuel loading method according to claim 1 , wherein the average fissile plutonium enrichment of the second fuel assembly is higher than the average fissile plutonium enrichment of the first fuel assembly. 10 . The fuel loading method according to claim 2 , wherein the average fissile plutonium enrichment of the second fuel assembly is higher than the average fissile plutonium enrichment of the first fuel assembly. 11 . A reactor core when transitioning from a first fuel assembly to a second fuel assembly in which at least one of an average uranium enrichment, an average fissile plutonium enrichment, and a fuel rod arrangement is different from that of the first fuel assembly, wherein when all fuel assemblies loaded in a region excluding an outermost periphery of the reactor core in an Nth operation cycle belong to the first fuel assembly, and all the fuel assemblies loaded in the region excluding the outermost periphery of the reactor core in a (N+m)th (m>1) operation cycle belong to the second fuel assembly, the number of new loaded second fuel assemblies in the (N+m) th operation cycle is greater than the number of new loaded second fuel assemblies in a (N+m−1)th operation cycle which is one operation cycle before the (N+m)th operation cycle, and a cycle burnup in the (N+m)th operation cycle is greater than a cycle burnup in the (N+m−1)th operation cycle. 12 . The reactor core according to claim 11 , wherein all the fuel assemblies in the reactor core in the Nth operation cycle belong to the first fuel assembly, and all the fuel assemblies in the reactor core in the (N+m) th operation cycle belong to the second fuel assembly. 13 . The reactor core according to claim 11 , wherein the first fuel assembly is a square grid fuel rod array of 9 rows and 9 columns, and the second fuel assembly is a square grid fuel rod array of 10 rows and 10 columns. 14 . The reactor core according to claim 12 , wherein the first fuel assembly is a square grid fuel rod array of 9 rows and 9 columns, and the second fuel assembly is a square grid fuel rod array of 10 rows and 10 columns. 15 . The reactor core according to claim 11 , wherein the first fuel assembly is a square grid fuel rod array of 10 rows and 10 columns, and the second fuel assembly is a square grid fuel rod array of 11 rows and 11 columns. 16 . The reactor core according to claim 12 , wherein the first fuel assembly is a square grid fuel rod array of 10 rows and 10 columns, and the second fuel assembly is a square grid fuel rod array of 11 rows and 11 columns. 17 . The reactor core according to claim 11 , wherein the average uranium enrichment of the second fuel assembly is higher than the average uranium enrichment of the first fuel assembly. 18 . The reactor core according to claim 12 , wherein the average uranium enrichment of the second fuel assembly is higher than the average uranium enrichment of the first fuel assembly. 19 . The reactor core according to claim 11 , wherein the average fissile plutonium enrichment of the second fuel assembly is higher than the average fissile plutonium enrichment of the first fuel assembly. 20 . The reactor core according to claim 12 , wherein the average fissile plutonium enrichment of the second fuel assembly is higher than the average fissile plutonium enrichment of the first fuel assembly.
Nuclear fission reactors · CPC title
characterised by the provision of more than one active zone · CPC title
comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods · CPC title
Boiling water reactors · CPC title
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