Solid interface joint with open pores for nuclear control rod
원문보기
IPC분류정보
국가/구분
United States(US) Patent
등록
국제특허분류(IPC7판)
G21C-007/08
G21C-007/10
G21C-021/18
출원번호
US-0704587
(2011-06-16)
등록번호
US-9620251
(2017-04-11)
우선권정보
FR-10 54781 (2010-06-16)
국제출원번호
PCT/EP2011/060001
(2011-06-16)
§371/§102 date
20130213
(20130213)
국제공개번호
WO2011/157782
(2011-12-22)
발명자
/ 주소
Zabiego, Maxime
David, Patrick
Ravenet, Alain
Rochais, Denis
출원인 / 주소
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
대리인 / 주소
Nixon Peabody, LLP
인용정보
피인용 횟수 :
1인용 특허 :
8
초록▼
A new interface between the cladding and the stack of pellets in a nuclear control rod. According to the invention, an interface joint made of a material transparent to neutrons, in the form of a structure with a high thermal conductivity and open pores, adapted to deform by compression across its t
A new interface between the cladding and the stack of pellets in a nuclear control rod. According to the invention, an interface joint made of a material transparent to neutrons, in the form of a structure with a high thermal conductivity and open pores, adapted to deform by compression across its thickness, is inserted between the cladding and the stack of pellets made of B4C neutron absorber material over at least the height of the stack. The invention also relates to associated production methods.
대표청구항▼
1. A nuclear control rod extending along a longitudinal direction (XX′), comprising a plurality of pellets, made of boron carbide B4C neutron absorber material, stacked on each other in the form of a column and a cladding surrounding the column of pellets, in which, the cladding and the pellets have
1. A nuclear control rod extending along a longitudinal direction (XX′), comprising a plurality of pellets, made of boron carbide B4C neutron absorber material, stacked on each other in the form of a column and a cladding surrounding the column of pellets, in which, the cladding and the pellets have a circular cross-section transverse to the longitudinal direction (XX′), and in which an interface joint, also with a circular cross-section transverse to the longitudinal direction (XX′), made of a material transparent to neutrons and is inserted between the cladding and the column of stacked pellets, at least over the height of the column, in which the interface joint is a structure, mechanically decoupled from the cladding and from the column of pellets, with a high thermal conductivity and open pores, adapted to deform by compression across its thickness so as to be compressed under the effect of the three-dimensional swelling of the pellets under irradiation, the initial thickness of the joint and its compression ratio being such that the mechanical load transmitted to the cladding by the pellets under irradiation remains less than a predetermined threshold value characterized in that the interface joint is made from a braid comprising a plurality of carbon fibre layers and a plurality of layers comprising silicon carbide fibres superposed on the carbon fibre layers. 2. The nuclear control rod according to claim 1, in which the open pores of the interface joint have a volume equal to at least 30% of the total volume of the interface joint as produced in fabrication. 3. The nuclear control rod according to claim 2, in which the open pores of the interface joint have a volume between 30% and 95% of the total volume of the interface joint as produced in fabrication. 4. The nuclear control rod according to claim 3, in which the open pores of the interface joint have a volume between 50% and 85% of the total volume of the interface joint as produced in fabrication. 5. The nuclear control rod according to claim 1, in which the thickness of the interface joint in its section transverse to the (XX′) direction is more than at least 10% of the radius of the pellets. 6. The nuclear control rod according to claim 1, in which the interface joint has a volume percentage of fibres between 15 and 50% and the open pores of the interface joint have a volume between 50% and 85% of the total volume of the interface joint as produced in fabrication. 7. The nuclear control rod according to claim 1, for a gas-cooled fast reactor (GFR), in which the basic material of the cladding is a refractory ceramic matrix composite (CMC) and the absorber pellets are made of B4C. 8. The nuclear control rod according to claim 1, for a sodium-cooled fast reactor (SFR), in which the cladding is made of a metallic material, and the absorber pellets are made of B4C. 9. The nuclear control rod according to claim 1, for Pressurized Water Reactors (PWR), or Boiling Water Reactors (BWR) in which the cladding comprises a refractory ceramic matrix composite CMC material and the absorber pellets are made of B4C. 10. Nuclear absorber assembly comprising a plurality of the nuclear control rods according to claim 1, and arranged to form a lattice. 11. A control rod according to claim 7, wherein the refractory ceramic matrix composite is SiC—SiCF.
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이 특허에 인용된 특허 (8)
Mordarski Walter J. (Wallingford CT), Chip sleeve for nuclear fuel elements.
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