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Power Burst Facility: U(18)O2-CaO-ZrO2 Fuel Rods in Water

• Authors : Bess, John

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Materials and mechanical design analysis of boron carbide reactor safety rods

• Authors : Marra, J

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Failure of latch mechanism for motion control of safety rods

• Authors : Leader, D

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Assessment of the influence of surface thermocouples on the behavior of nuclear fuel rods during a large break LOCA

• Authors : Yackle, T

• Source: Conference: 8. water reactor safety research information meeting, Gaithersburg, MD, USA, 27 Oct 1980

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Behavior of four PWR rods subjected to a simulated loss-of-coolant accient in the power burst facility

• Authors : Sepold, L

• Source: Conference: ANS meeting, Washington, DC, USA, 12 Nov 1978

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Measurements of heat-transfer coefficients, friction factors, and velocity profiles for air flowing parallel to closely spaced rods

• Authors : Swanson, Leonard

• Source: Conference: 2. International Heat Transfer Conference, Boulder, CO (United States) 28 Aug - 1 Sep 1961; Other Information: GA-1787; Other Information: Submitted for publication in the Conference

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Dynamic surface-pressure instrumentation for rods in parallel flow. [BWR; PWR]

• Authors : Lawrence, W.

• Source: Conference: Spring meeting of society for experimental stress analysis, San Francisco, CA, USA, 20 May 1979

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GAPCON-3: a computer code to analyze the path-dependent thermal and mechanical performance of nuclear fuel rods. [BWR and PWR]

• Authors : Stewart, K

• Source: Conference: The behaviour of water reactor fuel elements under accident conditions, Spaatind, Norway, 13 Sep 1976

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An investigation of scramming the outer shutdown rods of the ANS with no reversal of flow in the manifold inlet lines

• Authors : Morsk, K [Royal Inst. of Tech., Stockholm (Sweden)]

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Failure of expansion joint tie rods -- Impact on bellows integrity

• Authors : Miller, R

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