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Title: Nuclear reactor safety. Progress report, October 1-December 31, 1980

Development of the fast-running Transient Reactor Analysis Code (TRAC) version (PF1) continued during the quarter with numerical improvements and addition of a stratified-flow model. Independent assessment of the detailed version (PD2) continued with several Loss-Of-Fluid Test (LOFT) small-break tests, a PKL reflood test, and five Marviken critical-flow tests. Analysis efforts in the 2D/3D project concentrated on detailed investigations of Cylindrical-Core Test Facility (CCTF) Core I tests and calculated flow oscillations in the primary loops of the German pressurized water reactor (PWR). Investigations were completed of PWR transients involving emergency feed-water unavailability. Other Light-Water Reactor (LWR) safety progress included the use of the three-dimensional version of the SALE code to study hot-leg injection into the upper plenum and the effect of guide tube cross section on momentum flux. Efforts in Liquid-Metal-Cooled Fast-Breeder Reactor safety included studying transition-phase phenomena in an SNR-300-type reactor geometry using SIMMER and performing Upper Structure Dynamics experiments to examine rupture disk performance. In High-Temperature Gas-Cooled Reactor (HTGR safety, improvements were made to the Composite High-Temperature Gas-Cooled reactor Analysis Program (CHAP) code, and system transients in the Fort St. Vrain reactor were calculated. Other work in this area included thermal stress analyses of core support block response duringmore » fire-water cooldown following a loss-of-forced-circulation accident. Tests were run on steel cylinders to determine the effects of the Area Replacement Method on buckling strength as part of the Structural Margins-to-Failure program. In addition, a literature review was completed of models and experiments to determine damping and stiffness of reinforced concrete structures.« less
Authors:
;  [1]
  1. (comps.)
Publication Date:
OSTI Identifier:
5341449
Report Number(s):
NUREG/CR-2266; LA-8935-PR
ON: TI86000146
DOE Contract Number:
W-7405-ENG-36
Resource Type:
Technical Report
Research Org:
Los Alamos National Lab., NM (USA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; REACTOR SAFETY; RESEARCH PROGRAMS; COMPUTER CODES; CORE FLOODING SYSTEMS; FLOW MODELS; HTGR TYPE REACTORS; LMFBR TYPE REACTORS; LOSS OF COOLANT; REACTOR ACCIDENTS; STRESS ANALYSIS; THERMAL STRESSES; WATER MODERATED REACTORS; ACCIDENTS; BREEDER REACTORS; ECCS; ENGINEERED SAFETY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; LIQUID METAL COOLED REACTORS; MATHEMATICAL MODELS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; STRESSES 220900* -- Nuclear Reactor Technology-- Reactor Safety