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Ex-reactor deformation of externally pressurized short lengths of fuel rod cladding.

Description: The DECAG (Deformation of Cladding into Axial Gaps) ex-reactor test program evaluated deformation of Zircaloy-4 cladding into axial gaps in tubular fuel elements. These axial gaps are the result of cladding elongation and fuel stack shrinkage. The test program consisted of twelve series and subseries of both fully recrystallized and stress-relieved highly cold worked tubing tested under pressure-temperature combinations in autoclaves. The test program also verified the validity of achieving tes… more
Date: May 1, 1979
Creator: Selsley, I. A.
Item Type: Refine your search to only Report
open access

FLASH-6: simulation of top injection emergency core cooling heat transfer tests

Description: Data from top injection ECCS tests conducted at Columbia University have been analyzed as part of an effort to qualify the FLASH-6 computer program for performing post-blowdown heat transfer calculations for the LWBR Safety Analysis. These experiments, which employed a full-scale fuel assembly with electrical heater rods to simulate an inlet rupture for a pressurized water reactor, provided test conditions and rod cooling mechanisms quite similar to those encountered in the postulated LWBR cold… more
Date: May 1, 1977
Creator: Lincoln, F. W.
Item Type: Refine your search to only Report
open access

Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station

Description: This report summarizes the refueling operations performed to install a Light Water Breeder Reactor (LWBR) core into the existing pressurized water reactor vessel at the Shippingport Atomic Power Station. Detailed descriptions of the major installation operations (e.g., primary system preconditioning, fuel installation, pressure boundary seal welding) are included as appendices to this report; these operations are of technical interest to any reactor servicing operation, whether the reactor is a… more
Date: May 1, 1983
Creator: Massimino, R.J. & Williams, D.A.
Item Type: Refine your search to only Report
open access

PDQ-8 reference manual

Description: The PDQ-8 program is designed to solve the neutron diffusion, depletion problem in one, two, or three dimensions on the CDC-6600 and CDC-7600 computers. The three dimensional spatial calculation may be either explicit or discontinuous trial function synthesis. Up to five lethargy groups are permitted. The fast group treatment may be simplified P(3), and the thermal neutrons may be represented by a single group or a pair of overlapping groups. Adjoint, fixed source, one iteration, additive fixed… more
Date: May 1, 1978
Creator: Pfiefer, C J & Spitz, C J
Item Type: Refine your search to only Report
open access

Summary of several hydraulic tests in support of the light water breeder reactor design

Description: As part of the Light Water Breeder Reactor development program, hydraulic tests of reactor components were performed. This report presents the results of several of those tests performed for components which are somewhat unique in their application to a pressurized water reactor design. The components tested include: triplate orifices used for flow distribution purposes, multiventuri type flowmeters, tight lattice triangular pitch rod support grids, fuel rod end support plates, and the balance … more
Date: May 1, 1979
Creator: McWilliams, K. D. & Turner, J. R.
Item Type: Refine your search to only Report
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