JP2016125971A5 - - Google Patents

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JP2016125971A5
JP2016125971A5 JP2015001951A JP2015001951A JP2016125971A5 JP 2016125971 A5 JP2016125971 A5 JP 2016125971A5 JP 2015001951 A JP2015001951 A JP 2015001951A JP 2015001951 A JP2015001951 A JP 2015001951A JP 2016125971 A5 JP2016125971 A5 JP 2016125971A5
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fuel assemblies
reactor
fuel
cycle
nuclear reactor
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JP2015001951A
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JP6503188B2 (en
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また、本発明の原子炉の燃料集合体装荷方法は、(全燃料集合体体数)/(新燃料集合体体数)をMとしたとき、NはN≦Mを満たす最大の自然数であり、炉心の最外周に配される燃料集合体の外接円の半径をRとしたとき、前記外接円と同心円状で且つ、半径を略(R−45cm)とする境界領域を設定し、前記境界領域は内側炉心領域と外側炉心領域とを画定するものであり、前記外側炉心領域に配される燃料集合体は、炉内滞在期間が第N+2サイクル目以上の燃料集合体を少なくとも1体以上含み、且つ、(第N+2サイクル目以上の燃料集合体体数)/(第N+1サイクル目以上の燃料集合体体数)が0.6以下の関係を満たす原子炉炉心への燃料装荷方法であって、所定期間原子炉を運転した後、次の運転サイクルに移行する前に、前記外側炉心領域に配される燃料集合体のうち、第N+2サイクル目の燃料集合体を前記原子炉外に取り出し、前記外側炉心領域に配される燃料集合体のうち、第N+1サイクル目の燃料集合体は移動することなく、同一位置に配することを特徴とする。 Further, in the nuclear fuel assembly loading method of the present invention, when (total number of fuel assemblies) / (number of new fuel assemblies) is M, N is the maximum natural number satisfying N ≦ M. , when the radius of the circumscribed circle of the fuel assemblies disposed in the outermost periphery of the furnace center is R, and in the circumscribed circle and concentric sets a boundary region whose radius substantially (R-45cm), the The boundary region defines an inner core region and an outer core region, and the fuel assemblies arranged in the outer core region have at least one fuel assembly having a stay in the reactor of the N + 2th cycle or more. And a method of loading fuel into a nuclear reactor core that satisfies the following relationship: (number of fuel assemblies in the (N + 2) th cycle or more) / (number of fuel assemblies in the (N + 1) th cycle or more) After operating the reactor for a predetermined period, before moving to the next operation cycle The fuel assembly at the (N + 2) th cycle among the fuel assemblies arranged in the outer core region is taken out of the reactor, and the N + 1th cycle among the fuel assemblies arranged in the outer core region. The fuel assemblies are arranged at the same position without moving.

Claims (10)

複数の燃料集合体が装荷される原子炉の炉心であって、
(全燃料集合体体数)/(新燃料集合体体数)をMとしたとき、NはN≦Mを満たす最大の自然数であり、前記炉心の最外周に配される燃料集合体の外接円の半径をRとしたとき、前記外接円と同心円状で且つ、半径を略(R−45cm)とする境界領域を設定し、前記境界領域は内側炉心領域と外側炉心領域とを画定するものであり、
前記外側炉心領域に配される燃料集合体は、炉内滞在期間が第N+2サイクル目以上の燃料集合体を少なくとも1体以上含み、且つ、(第N+2サイクル目以上の燃料集合体体数)/(第N+1サイクル目以上の燃料集合体体数)が0.6以下の関係を満たすことを特徴とする原子炉炉心。
A nuclear reactor core loaded with a plurality of fuel assemblies,
When (total number of fuel assemblies) / (number of new fuel assemblies) is M, N is the maximum natural number that satisfies N ≦ M, and circumscribes the fuel assemblies arranged on the outermost periphery of the core. When a radius of a circle is R, a boundary region that is concentric with the circumscribed circle and has a radius of approximately (R-45 cm) is set, and the boundary region defines an inner core region and an outer core region And
The fuel assemblies arranged in the outer core region include at least one fuel assembly having a stay in the reactor of the (N + 2) th cycle or more, and (the number of fuel assemblies in the (N + 2) th cycle or more) / A reactor core characterized in that the number of fuel assemblies in the (N + 1) th cycle or more satisfies a relationship of 0.6 or less.
請求項1に記載の原子炉炉心において、
前記新燃料集合体は、前記内側炉心領域及び、最外周以外の前記外側炉心領域に配されることを特徴とする原子炉炉心。
The reactor core according to claim 1,
The nuclear reactor core according to claim 1, wherein the new fuel assembly is disposed in the inner core region and the outer core region other than the outermost periphery.
請求項1に記載の原子炉炉心において、
前記内側炉心領域に、相互に隣接する4体の炉内滞在期間が同一の燃料集合体が配され、前記4体の燃料集合体の配置位置は、複数の運転サイクルにおいて同一となることを特徴とする原子炉炉心。
The reactor core according to claim 1,
In the inner core region, four fuel assemblies having the same staying period in the reactor adjacent to each other are arranged, and the arrangement positions of the four fuel assemblies are the same in a plurality of operation cycles. Reactor core.
請求項2に記載の原子炉炉心において
前記外側炉心領域に配される燃料集合体であって、最外周に配される燃料集合体のうち所定数の燃料集合体は、複数の運転サイクルにおいて炉内滞在期間が同一であって、且つ、配置位置も同一であることを特徴とする原子炉炉心。
3. The nuclear reactor core according to claim 2, wherein the fuel assemblies are arranged in the outer core region, and a predetermined number of the fuel assemblies arranged in the outermost periphery are in a plurality of operating cycles. A reactor core characterized in that the in-stay period is the same and the arrangement position is also the same.
請求項3に記載の原子炉炉心において、
前記相互に隣接配置される4体の燃料集合体は、炉内滞在期間が第N+1サイクル目の燃料集合体であることを特徴とする原子炉炉心。
In the nuclear reactor core according to claim 3,
The four fuel assemblies arranged adjacent to each other are fuel assemblies whose stay in the reactor is in the (N + 1) th cycle.
請求項4に記載の原子炉炉心において、
前記最外周に配される燃料集合体のうち所定数の燃料集合体は、炉内滞在期間が第N+1サイクル目の燃料集合体であることを特徴とする原子炉炉心。
In the nuclear reactor core according to claim 4,
A nuclear reactor core characterized in that a predetermined number of fuel assemblies among the fuel assemblies arranged on the outermost periphery are fuel assemblies having a stay in the reactor at the (N + 1) th cycle.
請求項5又は請求項6に記載の原子炉炉心において、
前記Nは2以下であることを特徴とする原子炉炉心。
In the nuclear reactor core according to claim 5 or 6,
The nuclear reactor core characterized in that N is 2 or less.
(全燃料集合体体数)/(新燃料集合体体数)をMとしたとき、NはN≦Mを満たす最大の自然数であり、炉心の最外周に配される燃料集合体の外接円の半径をRとしたとき、前記外接円と同心円状で且つ、半径を略(R−45cm)とする境界領域を設定し、前記境界領域は内側炉心領域と外側炉心領域とを画定するものであり、
前記外側炉心領域に配される燃料集合体は、炉内滞在期間が第N+2サイクル目以上の燃料集合体を少なくとも1体以上含み、且つ、(第N+2サイクル目以上の燃料集合体体数)/(第N+1サイクル目以上の燃料集合体体数)が0.6以下の関係を満たす原子炉炉心への燃料装荷方法であって、
所定期間原子炉を運転した後、次の運転サイクルに移行する前に、前記外側炉心領域に配される燃料集合体のうち、第N+2サイクル目の燃料集合体を前記原子炉外に取り出し、
前記外側炉心領域に配される燃料集合体のうち、第N+1サイクル目の燃料集合体は移動することなく、同一位置に配することを特徴とする原子炉の燃料集合体装荷方法。
When the (total fuel assemblies number form) / (the new fuel assemblies number body) M, N is the largest natural number satisfying N ≦ M, circumscribing the fuel assemblies disposed in the outermost periphery of the furnace center When a radius of a circle is R, a boundary region that is concentric with the circumscribed circle and has a radius of approximately (R-45 cm) is set, and the boundary region defines an inner core region and an outer core region And
The fuel assemblies arranged in the outer core region include at least one fuel assembly having a stay in the reactor of the (N + 2) th cycle or more, and (the number of fuel assemblies in the (N + 2) th cycle or more) / A fuel loading method to a nuclear reactor core satisfying a relationship of (number of fuel assemblies in the (N + 1) th cycle or more) of 0.6 or less,
After operating the reactor for a predetermined period, before shifting to the next operation cycle, out of the fuel assemblies arranged in the outer core region, the fuel assembly at the (N + 2) th cycle is taken out of the reactor,
A fuel assembly loading method for a nuclear reactor, wherein, among the fuel assemblies arranged in the outer core region, the fuel assembly of the (N + 1) th cycle is arranged at the same position without moving.
請求項8に記載の原子炉の燃料集合体装荷方法において、
前記所定期間原子炉を運転した後、次の運転サイクルに移行する前に、前記新燃料集合体を、前記内側炉心領域及び最外周以外の前記外側炉心領域の所定の位置に装荷することを特徴とする原子炉の燃料集合体装荷方法。
The method of loading a fuel assembly for a nuclear reactor according to claim 8,
After operating the nuclear reactor for a predetermined period, before moving to the next operation cycle, the new fuel assembly is loaded at a predetermined position in the outer core region other than the inner core region and the outermost periphery. Reactor fuel assembly loading method.
請求項8に記載の原子炉の燃料集合体装荷方法において、
前記所定期間原子炉を運転した後、次の運転サイクルに移行する前に、前記内側炉心領域に相互に隣接する4体の炉内滞在期間が第N+1サイクル目の燃料集合体が配されていた位置に、第Nサイクル目の燃料集合体を移動することを特徴とする原子炉の燃料集合体装荷方法。
The method of loading a fuel assembly for a nuclear reactor according to claim 8,
After operating the reactor for the predetermined period, before moving to the next operation cycle, the fuel assemblies in the four (N + 1) th cycles in the reactor stay period adjacent to the inner core region were arranged. A fuel assembly loading method for a nuclear reactor, comprising moving an Nth cycle fuel assembly to a position.
JP2015001951A 2015-01-08 2015-01-08 Reactor core and fuel assembly loading method Active JP6503188B2 (en)

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CN109979630A (en) * 2017-12-27 2019-07-05 核动力运行研究所 A kind of fuel rod plug positioning device and method for fuel assembly reparation
CN108364696B (en) * 2018-02-13 2019-09-03 中国核动力研究设计院 A kind of 100,000 kilowatts of order reaction heap reactor core reactivity control methods
CN108364695B (en) * 2018-02-13 2019-09-03 中国核动力研究设计院 A kind of 100,000 kilowatts of order reaction heap in-core fuel management methods

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JPS58178286A (en) * 1982-04-12 1983-10-19 株式会社東芝 Bwr type reactor
JPS60100086A (en) * 1983-11-04 1985-06-03 株式会社日立製作所 Core for nuclear reactor
JPS60262090A (en) * 1984-06-11 1985-12-25 株式会社日立製作所 Nuclear reactor
JPH067194B2 (en) * 1985-10-23 1994-01-26 株式会社日立製作所 Light water reactor core and its fuel loading method
JPH05346477A (en) * 1992-06-15 1993-12-27 Toshiba Corp Arranging method for fuel of boiling water reactor
JP3107290B2 (en) * 1996-05-20 2000-11-06 株式会社日立製作所 Fuel loading method
JPH11248872A (en) * 1998-03-06 1999-09-17 Hitachi Ltd Reactor core and method for operating it
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