Nuclear fuel pellet laminate structure having enhanced thermal conductivity and method for manufacturing the same

1. A nuclear fuel pellet laminate structure having enhanced thermal conductivity, comprising:

a nuclear fuel pellet; and

a thermally conductive metal layer disposed above or below the nuclear fuel pellet,

wherein the nuclear fuel pellet is a nuclear fuel matrix, and does not include thermally conductive metal powder,

wherein a ratio of a diameter to a height of the nuclear fuel pellet is in a range of 1.6 to 2.0,

wherein formation of impurities due to chemical reactions of the thermally conductive metal layer is suppressed,

wherein the impurity comprises one or more selected from the group consisting of a thermally conductive metal hydride, a thermally conductive metal oxide, a thermally conductive metal nitride, a thermally conductive metal-uranium compound, a thermally conductive metal-plutonium compound, and a thermally conductive metal-thorium compound,

wherein the thermally conductive metal layer is a plate shape, a cross shape or radial shape for connecting a peripheral portion in contact with a nuclear fuel cladding tube in a radial direction from the center, and

wherein the thermally conductive metal layer comprises one or more selected from the group consisting of molybdenum (Mo), chromium (Cr), tungsten (W), niobium (Nb), ruthenium (Ru), vanadium (V), hafnium (Hf), tantalum (Ta), rhodium (Rh), zirconium (Zr), beryllium (Be), and aluminum (Al).

2. The nuclear fuel pellet laminate structure of claim 1 , wherein the height of the nuclear fuel pellet is 3 mm to 6 mm.

3. The nuclear fuel pellet laminate structure of claim 1 , wherein the content of the thermally conductive metal layer is 1 wt. % to 10 wt. % based on the total weight of the nuclear fuel pellet.

4. A method for manufacturing a nuclear fuel pellet laminate structure having enhanced thermal conductivity, comprising:

(a) a step of molding and thermally treating nuclear fuel powder to manufacture a nuclear fuel pellet; and

(b) a step of disposing a thermally conductive metal layer above or below the nuclear fuel pellet manufactured in step (a),

wherein the nuclear fuel pellet is a nuclear fuel matrix, and does not include thermally conductive metal powder,

wherein a ratio of a diameter to a height of the nuclear fuel pellet is in a range of 1.6 to 2.0,

wherein formation of impurities due to chemical reactions of the thermally conductive metal layer is suppressed,

wherein the impurity comprises one or more selected from the group consisting of a thermally conductive metal hydride, a thermally conductive metal oxide, a thermally conductive metal nitride, a thermally conductive metal-uranium compound, a thermally conductive metal-plutonium compound, and a thermally conductive metal-thorium compound,

wherein the thermally conductive metal layer is a plate shape, a cross shape or radial shape for connecting a peripheral portion in contact with a nuclear fuel cladding tube in a radial direction from the center, and

wherein the thermally conductive metal layer comprises one or more selected from the group consisting of molybdenum (Mo), chromium (Cr), tungsten (W), niobium (Nb), ruthenium (Ru), vanadium (V), hafnium (Hf), tantalum (Ta), rhodium (Rh), zirconium (Zr), beryllium (Be), and aluminum (Al).

5. The method of claim 4 , wherein the molding in step (a) is performed for 30 seconds to 20 hours under a pressure of 100 MPa to 500 MPa, and the thermally treating is performed for 1 hour to 20 hours at a temperature of 1,300° C. to 1,800° C. under a hydrogen atmosphere.

6. The method of claim 4 , wherein the disposing of the thermally conductive metal layer in step (b) is performed through one or more methods selected from the group consisting of a coating method, a vapor deposition method, and a three-dimensional printing method.