Reactivity Initiated Accident Test Series: Test RIA 1-2. Quick look report. [BWR hot start-up conditions]

Title: Reactivity Initiated Accident Test Series: Test RIA 1-2. Quick look report. [BWR hot start-up conditions]

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Abstract

The primary objectives of Test RIA 1-2 were to (a) characterize the response of preirradiated fuel rods during an RIA event conducted at boiling water reactor (BWR) hot-startup conditions for an axial peak pellet surface energy of 200 cal/g UO/sub 2/, and (b) evaluate the effect of internal rod pressure on preirradiated fuel rod response during an RIA event. The test consisted of four, individually shrouded, pressurized water reactor-type fuel rods previously irradiated to burnups of about 4800 MWd/t. In addition to the power calibration and preconditioning, the fuel rods were subjected to a single power burst that deposited a total pellet surface energy of approximately 200 cal/gm UO/sub 2/ at the axial peak power location (estimated using the core power chambers to relate steady state and transient powers). The test data indicate that the two irradiated fuel rods prepressurized to 2.41 MPa did not fail. FRAP-T4 calculations had predicted that prompt cladding rupture would occur for pellet surface energy depositions of 206 cal/g or greater. Although the two fuel rods prepressurized to 2.41 MPa did not fail, the data indicate that at least one of the two fuel rods prepressurized to 0.1 MPa did fail. Based on the coremore »« less

Authors:: Martinson, Z R; Semken, R S; Smith, R H; Osetek, D J

Publication Date:: 1978-12-01

Research Org.:: Idaho National Engineering Lab., Idaho Falls (USA)

OSTI Identifier:: 6451962

Report Number(s):: TFBP-TR-303
TRN: 79-002890

DOE Contract Number:: EY-76-C-07-1570

Resource Type:: Technical Report

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; BWR TYPE REACTORS; EXCURSIONS; FUEL ELEMENT FAILURE; BURNUP; PRESSURE GRADIENTS; REACTOR START-UP; SIMULATION; ACCIDENTS; REACTOR ACCIDENTS; REACTORS; START-UP; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety

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                    Martinson, Z R, Semken, R S, Smith, R H, and Osetek, D J. Reactivity Initiated Accident Test Series: Test RIA 1-2. Quick look report. [BWR hot start-up conditions].  United States: N. p., 1978. 
        Web.

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                    Martinson, Z R, Semken, R S, Smith, R H, & Osetek, D J. Reactivity Initiated Accident Test Series: Test RIA 1-2. Quick look report. [BWR hot start-up conditions].  United States.

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                    Martinson, Z R, Semken, R S, Smith, R H, and Osetek, D J. Fri .  
        "Reactivity Initiated Accident Test Series: Test RIA 1-2. Quick look report. [BWR hot start-up conditions]".  United States.

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@article{osti_6451962,

  title        = {Reactivity Initiated Accident Test Series: Test RIA 1-2. Quick look report. [BWR hot start-up conditions]},

  author       = {Martinson, Z R and Semken, R S and Smith, R H and Osetek, D J},

  abstractNote = {The primary objectives of Test RIA 1-2 were to (a) characterize the response of preirradiated fuel rods during an RIA event conducted at boiling water reactor (BWR) hot-startup conditions for an axial peak pellet surface energy of 200 cal/g UO/sub 2/, and (b) evaluate the effect of internal rod pressure on preirradiated fuel rod response during an RIA event. The test consisted of four, individually shrouded, pressurized water reactor-type fuel rods previously irradiated to burnups of about 4800 MWd/t. In addition to the power calibration and preconditioning, the fuel rods were subjected to a single power burst that deposited a total pellet surface energy of approximately 200 cal/gm UO/sub 2/ at the axial peak power location (estimated using the core power chambers to relate steady state and transient powers). The test data indicate that the two irradiated fuel rods prepressurized to 2.41 MPa did not fail. FRAP-T4 calculations had predicted that prompt cladding rupture would occur for pellet surface energy depositions of 206 cal/g or greater. Although the two fuel rods prepressurized to 2.41 MPa did not fail, the data indicate that at least one of the two fuel rods prepressurized to 0.1 MPa did fail. Based on the core power chamber data, this rod failure indicates a threshold for the preirradiated fuel rods near or below 200 cal/g UO/sub 2/ total pellet surface energy at the axial flux peak.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/6451962},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1978},

  month        = {12}

}

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