Determination of Appendix K Conservatisms for Large Break LOCA in a Westinghouse PWR Using TRAC-PD2/MOD1 CodeLWR Code Assessment and Application Group, Brookhaven National Laboratory, Department of Nuclear Energy, 1986 - Pressurized water reactors - 99 pages |
Common terms and phrases
accident additional Appendix K guidelines approximately average average rod BEST ESTIMATE MODEL best-estimate break flow bypass CELL Clad surface temperature cold leg Comparison component conservatism containment contributed coolant cooling core inlet deck decreased downcomer ECCS EM-type calculations EM1 calculation ESTIMATE MODEL TRANSIENT EVALUATION MODEL fluid four axial locations fuel heat transfer hot channel hot leg hot rod increased INEL Initially input Intact Loop LANL leg flow licensing liquid fraction Liquid Mass Flow LOCA Loop Accumulator loop hot leg loss lower plenum mass flow rate occurred oscillations peak clad temperature performed physical models PIPE plant prediction Pressurizer Loop PRIMARY pump quadrant RCPs Reactor reflood phase Report represented ROD TEMPERATURE DEG-K safety injection saturation scenario seconds shown in Figure shows started system pressure Table temperatures at four tion updates VESSEL ID void fraction Water Level Westinghouse