US3342692A - Moderator-fuel element - Google Patents

Moderator-fuel element Download PDF

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Publication number
US3342692A
US3342692A US540594A US54059466A US3342692A US 3342692 A US3342692 A US 3342692A US 540594 A US540594 A US 540594A US 54059466 A US54059466 A US 54059466A US 3342692 A US3342692 A US 3342692A
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US
United States
Prior art keywords
moderator
fuel
yttrium
molybdenum
hydride
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.)
Expired - Lifetime
Application number
US540594A
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English (en)
Inventor
Bourrasse Andre
Carteret Yvette
Elston Jean
Lucas Renee
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique CEA
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/16—Details of the construction within the casing
    • G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • 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

Definitions

  • This invention relates to a moderator-fuel element which is primarily intended to be employed in nuclear reactors for spacecraft, and also to a method of manufacture of said element or a like element.
  • reactors of this type are lightness of weight and small bulk. It is consequently an advantage to make use of moderator-fuel elements containing spherical particles of enriched fuel which are dispersed in a solid moderator formed of a metal hydride having a high hydrogen concentration. Zirconium hydride is mainly employed for this purpose.
  • Elements of this type are clad with a protective jacket or can for retention of fission gases and hydrogen and are arranged in parallel clusters between which cooling fluid is circulated.
  • the cooling fluid is cooled by means of a secondary fluid circuit comprising a radiator which is cooled by radiation in space.
  • a secondary fluid circuit comprising a radiator which is cooled by radiation in space.
  • the present invention is concerned with a moderatorfuel element which is primarily intended for use in reactors for space vehicle propulsion and which affords the same advantages as the elements of the prior art referredto above but which can additionally be utilized under good conditions at temperatures of a much higher order.
  • the moderator-fuel element in accordance with the invention which contains spherical particles of refractory fuel dispersed in a solid moderator, is characterized in that said moderator consists of yttrium hydride, the spherical particles of refractory fuel being coated with a layer of material which does not react with yttrium hydride, such as molybdenum.
  • Yttrium hydride is stable at temperatures which can exceed 900 C. to 1,000 C. and, even at these temperatures, still has a hydrogen concentration of more than 5.1022 atoms per cm?. This concentration permits of excellent neutron economy in respect of a very small volume of moderator.
  • the intended function of the coating which is applied over the spherical fuel particles is to prevent the yttrium from attacking the fuel by preventing any contact between these latter. It has been observed, for example, that uranium oxide is reduced by yttrium at 1,000 C.; uranium carbide is also attacked. On the other hand, it has been found that molybdenum and other compounds such as SiC, MoSi2 and BeO remain compatible with yttrium at temperatures of the order of l,000 C.
  • the moderator-fuel element is clad with a jacket or can of molybdenum or of a refractory alloy (Hastelloy or Inconel, for example) which is lined internally with an impervious layer for inhibiting diffusion of hydrogen.
  • This layer can be formed in particular of a nitride, carbide, silicide, boride or even oxide formed, for example, by suitable treatment of the can.
  • the composition of the anti-diffusion layer which is provided it may prove necessary or advantageous to form an intermediate metallic layer between the moderator and the can, for example in order to prevent any reaction between a silicate-base enamel and the yttrium hydride.
  • the present invention is also concerned with a method of fabrication of the moderator-fuel element as hereinabove defined or of any element of like nature.
  • This method is characterized in that it consists in grinding the yttrium, in mixing the ground product with particles of refractory fuel which have previously been coated with a material which does not react with yttrium, in siutering said mixture, in placing the sintered product in a metal can after machining if necessary, then in hydriding the mass of yttrium.
  • the sintering of the ground yttrium which contains the fuel is preferably carried out at a temperature of the order of 1,000" C. after hydrostatic pressing under a pressure in the vicinity of l t./cm.2.
  • Hydriding can be carried out in particular by placing the element in a hydrogen atmosphere at a pressure of the order of mm. of mercury at 1 atmosphere and at a temperature ranging from 800 to 900 C. Once the hydriding process is completed, the hydrogen pressure is preferably adjusted tO approximately 200 mm. of mercury.
  • the element described is intended to be employed in a reaction which is cooled by circulation of NaK.
  • Said element consists of a cylindrical rod 1 having a diameter of l5 mm. and made up of spherical fuel particles 2 dispersed in an yttrium hydride matrix which constitutes the moderator.
  • the fuel which is employed in the particular case herein described is uranium oxide U02.
  • any other refractory fuel such as a carbide, a silicide or a nitride.
  • the spherical fuel particles which are approximately u in diameter, are provided with a thin coat of molybdenum having a thickness Within the range of 3 to 10,1.
  • the rod 1 is contained in a molybdenum can 3 which is lined with an enamel layer 4 having a thickness of 0.3 mm.
  • the thickness of the molybdenum can itself is also in the vicinity of 0.3 mm.
  • the purpose of the enamel coating is to prevent any diffusion of hydrogen through the can.
  • the can 3 is of greater length than the rod 1.
  • a hollow cylindrical end-cap 5 which is also formed of molybdenum is fitted in the end of the can.
  • the base 6 of said end-cap is provided on the side facing the rod 1 with an enamel coating 7 which completes the enamel lining of the can itself.
  • a magnesia pellet 8 is interposed between the end of the rod 1 and the end-cap 5. The intended function of said pellet is to prevent any contact between the enamel and the yttrium hydride, while at the same time ensuring thermal insulation so as to prevent any over-heating of
  • the initial operation consists in mixing the yttrium powder withthe fuel particles which have been previously coated with molybdenum.
  • the sinteririgk of the powdered mixture is then carried out.
  • This sintering process is advantageously ycarried out at a temperature within the range of 1,000 to 1,200" ⁇ C. and preferably in the vicinity of 1,000 C., after hydrostatic pressing under a pressure ranging from approxi'- mately 1 t./cm.2 to 5 lt./cm.2.
  • the density of ⁇ the product thus obtained is in the vicinity of 95% of theoretical.
  • the rod thus obtained mayif necessary be machined to the desired size. It is inserted in the enamelled molybl denum can which is lined with a continuous molybdenum film, then hydrided in situ. This operation is performed at 850 C. at a pressure of 200 mm. of mercury.
  • the advantage of this method lies inthe fact that it avoids manipulation of the hydride which is ybothvbrittle and difficult to machine.
  • the method also makes it possiblek to establish good thermal Contact between the enamelled can and the moderator, in View .of the fact that the hydriding process results in an increase in volume of the order of 5.6% under the operating conditions hereinabove described, wherein the end product ⁇ obtained is a hydride corresponding to the formula YHl, 85.
  • the proton concentration obtained under the same conditions is of the order of 5.10"2 nuclei of ,hydrogen per cm.
  • magnesia pellet is then inserted in the can until it is brought into. contact with ⁇ the rod, followedby the molybdenum end-cap.
  • the enamelling of the end-cap is carried out by high frequency heating so as to ensure the continuity of the imperviouslining.
  • Moderator-fuel element containing refractory-fuel particles dispersed in a solid moderator consisting of yttrium hydride, said refractory-fuel particles being coated with a layer of molybdenum.
  • Moderator-fuel element in accordance with claim 1 including a molybdenum can surrounding said moderator and an anti-diffusion'layer formed betweenthe solid mod erator and said can so as to prevent the diiusion of hydrogen.
  • Moderator-fuel element inraccordance with claim 2 wherein said anti-diffusion layer consists of an enamel having a base of aluminum silicate and zirconium silicate and is separated from the yttrium hydride by an intermediate protective layer.
  • Moderator-fuel element in accordance with claim 3, wherein said intermediate layer is formed of molybdenum.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Fuel Cell (AREA)
  • Silicon Compounds (AREA)
US540594A 1965-04-26 1966-04-06 Moderator-fuel element Expired - Lifetime US3342692A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR14664A FR1441629A (fr) 1965-04-26 1965-04-26 élément modérateur-combustible

Publications (1)

Publication Number Publication Date
US3342692A true US3342692A (en) 1967-09-19

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US540594A Expired - Lifetime US3342692A (en) 1965-04-26 1966-04-06 Moderator-fuel element

Country Status (6)

Country Link
US (1) US3342692A (enrdf_load_stackoverflow)
BE (1) BE679037A (enrdf_load_stackoverflow)
CH (1) CH455069A (enrdf_load_stackoverflow)
FR (1) FR1441629A (enrdf_load_stackoverflow)
GB (1) GB1107300A (enrdf_load_stackoverflow)
LU (1) LU50956A1 (enrdf_load_stackoverflow)

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5169794A (enrdf_load_stackoverflow) * 1974-11-11 1976-06-16 Gen Electric
JPS5169793A (enrdf_load_stackoverflow) * 1974-11-11 1976-06-16 Gen Electric
US3994778A (en) * 1971-07-15 1976-11-30 The United States Of America As Represented By The United States Energy Research And Development Administration Liquid metal hydrogen barriers
US4032400A (en) * 1976-02-17 1977-06-28 The United States Of America As Represented By The United States Energy Research And Development Administration Nuclear reactor fuel element with vanadium getter on cladding
US4123326A (en) * 1974-05-22 1978-10-31 Hitachi, Ltd. Nuclear fuel element and method for fabricating the nuclear fuel element
US4652427A (en) * 1983-04-06 1987-03-24 Hitachi, Ltd. Fuel assembly
US4751041A (en) * 1986-01-15 1988-06-14 Westinghouse Electric Corp. Burnable neutron absorber element
US6233299B1 (en) * 1998-10-02 2001-05-15 Japan Nuclear Cycle Development Institute Assembly for transmutation of a long-lived radioactive material
CN111276265A (zh) * 2019-12-31 2020-06-12 中国核动力研究设计院 一种采用铀-氢化钇燃料的棒型燃料元件
CN113969361A (zh) * 2021-10-27 2022-01-25 中国核动力研究设计院 高纯钇的制备方法、氢化钇芯块的制备方法及氢化钇芯块
US11443858B2 (en) * 2020-07-10 2022-09-13 Uchicago Argonne, Llc Neutron moderation modules
CN117735987A (zh) * 2023-11-09 2024-03-22 中国科学院上海应用物理研究所 一种基于燃料颗粒的氢化钇基体燃料元件及其制备方法以及应用

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114804028B (zh) * 2022-05-09 2024-04-30 西安稀有金属材料研究院有限公司 一种空间堆用无裂纹氢化钇中子慢化材料及其制备方法
CN116110619A (zh) * 2023-02-10 2023-05-12 中国核电工程有限公司 气冷微堆燃料组件及气冷微堆堆芯系统

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3088892A (en) * 1960-05-05 1963-05-07 Jr Francis M Cain Dispersion element consisting of chromium coated uo2 particles uniformly distributedin a zircaloy matrix
US3096263A (en) * 1952-04-01 1963-07-02 Walter E Kingston Nuclear reactor fuel elements and method of preparation
US3121047A (en) * 1961-03-16 1964-02-11 Lincoln D Stoughton Ceramic coated fuel particles
US3154845A (en) * 1962-02-08 1964-11-03 Gen Dynamics Corp Method of fabricating a fuel element
US3167655A (en) * 1960-08-30 1965-01-26 Redstone Reuben Target for a neutron generator consisting of a coating of one of the lanthanon elements on a base metal
US3170847A (en) * 1959-12-15 1965-02-23 Joseph A Dudek Self-moderating fuel element

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3096263A (en) * 1952-04-01 1963-07-02 Walter E Kingston Nuclear reactor fuel elements and method of preparation
US3170847A (en) * 1959-12-15 1965-02-23 Joseph A Dudek Self-moderating fuel element
US3197389A (en) * 1959-12-15 1965-07-27 Joseph A Dudek Method for fabricating self-moderating nuclear reactor fuel element
US3088892A (en) * 1960-05-05 1963-05-07 Jr Francis M Cain Dispersion element consisting of chromium coated uo2 particles uniformly distributedin a zircaloy matrix
US3167655A (en) * 1960-08-30 1965-01-26 Redstone Reuben Target for a neutron generator consisting of a coating of one of the lanthanon elements on a base metal
US3121047A (en) * 1961-03-16 1964-02-11 Lincoln D Stoughton Ceramic coated fuel particles
US3154845A (en) * 1962-02-08 1964-11-03 Gen Dynamics Corp Method of fabricating a fuel element

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3994778A (en) * 1971-07-15 1976-11-30 The United States Of America As Represented By The United States Energy Research And Development Administration Liquid metal hydrogen barriers
US4123326A (en) * 1974-05-22 1978-10-31 Hitachi, Ltd. Nuclear fuel element and method for fabricating the nuclear fuel element
JPS5169794A (enrdf_load_stackoverflow) * 1974-11-11 1976-06-16 Gen Electric
JPS5169793A (enrdf_load_stackoverflow) * 1974-11-11 1976-06-16 Gen Electric
US4032400A (en) * 1976-02-17 1977-06-28 The United States Of America As Represented By The United States Energy Research And Development Administration Nuclear reactor fuel element with vanadium getter on cladding
US4652427A (en) * 1983-04-06 1987-03-24 Hitachi, Ltd. Fuel assembly
US4751041A (en) * 1986-01-15 1988-06-14 Westinghouse Electric Corp. Burnable neutron absorber element
US6233299B1 (en) * 1998-10-02 2001-05-15 Japan Nuclear Cycle Development Institute Assembly for transmutation of a long-lived radioactive material
CN111276265A (zh) * 2019-12-31 2020-06-12 中国核动力研究设计院 一种采用铀-氢化钇燃料的棒型燃料元件
US11443858B2 (en) * 2020-07-10 2022-09-13 Uchicago Argonne, Llc Neutron moderation modules
CN113969361A (zh) * 2021-10-27 2022-01-25 中国核动力研究设计院 高纯钇的制备方法、氢化钇芯块的制备方法及氢化钇芯块
CN117735987A (zh) * 2023-11-09 2024-03-22 中国科学院上海应用物理研究所 一种基于燃料颗粒的氢化钇基体燃料元件及其制备方法以及应用

Also Published As

Publication number Publication date
CH455069A (fr) 1968-04-30
BE679037A (enrdf_load_stackoverflow) 1966-09-16
GB1107300A (en) 1968-03-27
FR1441629A (fr) 1966-06-10
LU50956A1 (enrdf_load_stackoverflow) 1966-06-27

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