Search Results

open access

In-pile temperature dependence of the yield strength and growth of Zircaloy

Description: A previously reported growth model is modified and low temperature growth predictions in Zircaloy are made to support the proposal that the smaller irradiation damage observed at lower temperature results from the damage sites, or depleted zones, being larger at lower temperatures. This proposal holds that the vacancies making up the zones cannot migrate at the lower temperature and, therefore, cannot condense into small voids or dislocation loops. The larger zones serve as better sinks for int… more
Date: March 1978
Creator: Dollins, C. C.
Partner: UNT Libraries Government Documents Department
open access

Irradiation testing of internally pressurized and/or graphite coated Zircaloy-4 clad fuel rods in the NRX Reactor (AWBA Development Program). [LWBR]

Description: Irradiation tests on 0.612 inch O.D. by 117-inch long Zircaloy-4 clad fuel rods were performed to assess the effects on fuel rod performance of (1) internal helium pre-pressurization to 500 psi as fabricated, (2) the presence of a graphite barrier coating on the inside cladding surface, and (3) combined pre-pressurization and graphite coating. Periodic dimensional examinations were performed on the test rods, and the results were compared with data obtained from two previously irradiated test r… more
Date: November 1, 1978
Creator: Hoffman, R.C. & Sherman, J.
Partner: UNT Libraries Government Documents Department
open access

Model to predict swelling, gas release, and densification in oxide fuels

Description: A model was developed to predict in-pile fission gas swelling, gas release, and densification in oxide fuels. This model considers fission gas behavior at the grain interior, on the grain boundaries, and at grain boundary edges under conditions of total gas bubble destruction by fission fragments and partial gas bubble destruction. When gas bubble swelling on grain edges reaches 5 percent, it is assumed that gas tunnels form along the edges. Gas release takes place by migration of the gas in th… more
Date: June 1, 1978
Creator: Dollins, C. C.
Partner: UNT Libraries Government Documents Department
open access

Spatial distribution measurements of fission neutrons in water as an oxygen data test

Description: The spatial distribution of the total neutron density from a /sup 252/Cf source in pure water was measured to high statistical precision at distances from 11 to 80 cm from the source. Assuming the adequacy of the ENDF/B-IV hydrogen, and reasonable constraints on the fission spectrum mean energy, good agreement between experiment and a one-dimensional transport calculation was obtained for both ENDF/B-III and IV oxygen, with Version III slightly better. However, small residual differences remain… more
Date: February 1978
Creator: Green, L. & Ullo, J.J.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen