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Applied Science & Technology Full Text (H.W. Wilson)

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A new generation of uranium coincidence fast neutron collars for assay of LWR fresh fuel assemblies.

• Authors : Swinhoe, M.T.¹ (AUTHOR) ; Menlove, H.O.¹ (AUTHOR); de Baere, P.² (AUTHOR)

Subjects: *BOILING water reactors; *PRESSURIZED water reactors; *FAST neutronsLOS Alamos National Laboratory ; UNITED States. Dept. of Energy

• Source: Nuclear Instruments & Methods in Physics Research Section A. Sep2021, Vol. 1009, pN.PAG-N.PAG. 1p.

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Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR.

• Authors : Al-Zahrani, Yahya A.¹ (AUTHOR) ; Mehboob, Khurram¹ (AUTHOR) ; Mohamad, Daud¹ (AUTHOR)

Subjects: *FAST reactors; *BOILING water reactors; *URANIUM oxides

• Source: Annals of Nuclear Energy. Jun2021, Vol. 155, pN.PAG-N.PAG. 1p.

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Japan : Hitachi Begins Joint Research with Three American Universities Targeting Resource-renewable Boiling Water Reactors that can Reduce the Time Required for Decay in the Radioactivity of Waste Mat.

• Source: Mena Report. 2014.

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Japan: Hitachi Begins Joint Research with Three American Universities Targeting Resource-renewable Boiling Water Reactors that can Reduce the Time Required for Decay in the Radioactivity of Waste Mat.

• Source: TendersInfo News. 2014.

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A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors.

• Authors : Vasiliev, Alexander¹ (AUTHOR) ; Grimm, Peter¹ (AUTHOR) ; Ferroukhi, Hakim¹ (AUTHOR)

Subjects: *BOILING water reactors; *URANIUM; *WATER chemistry

• Source: Annals of Nuclear Energy. Sep2020, Vol. 144, pN.PAG-N.PAG. 1p.

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Design of an MCNPX model to simulate the performance of BWRs using thorium as fuel and its validation with HELIOS code.

• Authors : Abdelghafar Galahom, A.¹ ; Bashter, I.I.²; Aziz, Moustafa³

Subjects: *BOILING water reactors; *THORIUM dioxide; *URANIUM

• Source: Annals of Nuclear Energy. Mar2015, Vol. 77, p393-401. 9p.

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KRITZ-1-Mk CRITICAL MEASUREMENTS AT TEMPERATURES FROM 20 °C TO 250 °C.

• Authors : Margulis, M.; Blaise, P.; Mennerdahl, Dennis

Subjects: NUCLEAR reactor reactivity; URANIUM; NUCLEAR fuels

• Source: EPJ Web of Conferences; 2021, Vol. 247, p1-8, 8p

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Fuel lattice design with Path Relinking in BWR’s

• Authors : Castillo, Alejandro¹ ; Ortiz-Servin, Juan José¹ ; Perusquía, Raúl¹

Subjects: *BOILING water reactors; *FUEL; *LATTICE theory

• Source: Progress in Nuclear Energy. May2011, Vol. 53 Issue 4, p368-374. 7p.

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