Post-stressed concrete foundation may reduce machinery vibration

Post-stressing concrete mat foundation reduces excessive vibrations in machinery. The mat is stressed in compression after the machinery is mounted, thus closing any cracks in it, altering the distribution of the soil subgrade reaction on the mat, and changing the mat-subgrade natural frequency

Hydrodynamics of a new concept of primary containment by energy absorption

Fluid dynamical analysis for idealized reactors system with spherical symmetry determines the effect which the destructive component of a nuclear accident produces on primary containment structures. Steel strands surrounding the reactor cavity in the biological shield exhibit plastic deformation to achieve the energy absorption

Structural and containment response to LMFBR accidents

The adequacy of the containment of fast reactors has been traditionally evaluated by analyzing the response of the containment to a spectrum of core disruptive accidents. The current approach in the U.S. is to consider fast reactor response to accidents in terms of four lines of assurance (LOAs). Thus, LOA-1 is to prevent accidents, LOA-2 is to limit core damage, LOA-3 is to control accident progression and LOA-4 is to attenuate radiological consequences. Thus, the programs on the adequacy of containment response fall into LOA-3. Significant programs to evaluate the response of the containment to core disruptive accidents and, thereby, to assure control of accident progression are in progress. These include evaluating the mechanical response of the primary system to core disruptive accidents and evaluating the thermal response of the reactor structures to core melting, including the effects this causes on the secondary containment. The analysis of structural response employs calculated pressure-volume-time loading functions. The results of the analyses establish the response of the containment to the prescribed loadings. The analysis of thermal response requires an assessment of the distribution and state of the fuel, fission products and activated materials from accident initiation to final disposition in a stable configuration

Argonne National Laboratory Report ANL-6781

Report containing experiments regarding the slopes and deflections of different grid support structures for a nuclear reactor

Analysis of HCDA loads and containment response of a large loop-type LMFBR

As part of a comprehensive safety study, analyses are presented on the hydrodynamic loads and containment response of a large loop-type LMFBR subjected to an HCDA of a 1000 MJ energy release. The reference reactor consists of a primary vessel, a head cover, and various complex internals such as the upper internal structure (UIS), the core-support structure (CSS), radial shield, shield baffles, and deflector plate. Three calculations are performed with the ANL hybrid Lagrangian-Eulerian containment code, ALICE-II. They deal, respectively, with: (1) the calculation of HCDA hydrodynamics, reactor-cover loads, and forces on the UIS; (2) investigating the mitigating effect of the UIS on the cover loading as well as the containment response; and (3) the analysis of overall containment integrity, including interaction of fluids with the deformable UIS and CSS

Argonne National Laboratory Reports

From Summary: "The strains in the walls and ceiling of Cell No. 5 were recorded with 39 SR-4 strain gages strategically placed on reinforcing steel. Table I summarizes the comparative results without including correction for stress concentrations. The general pattern of cell behavior at 10 psig, as summarized in Table I, is shown in Figs. 10, 11, 12.

Design criteria for steel in nuclear reactors /

"AEC Research and Development Report""(TID-4500, 16th Ed., Amended)""Metals, Ceramics, and Materials"Bibliography: p. 18-19.Operated by The University of ChicagoMode of access: Internet