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

Technical Report · Tue Sep 01 00:00:00 EDT 1981

OSTI ID:5341449

Stevenson, M G; Vigil, J C ^[1]

---

1. comps.

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 during 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.

• Research Organization: Los Alamos National Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5341449
• Report Number(s): NUREG/CR-2266; LA-8935-PR; ON: TI86000146
• Country of Publication: United States
• Language: English

Related Subjects

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