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Biaxial Creep Behavior of Ribbed GCFR Cladding at 650 degrees C in Nominally Pure Helium (99. 99%)

Description: Biaxial creep-rupture tests were conducted on 12 prototypic GCFR fuel-cladding specimens at 650 deg C and a nominal hoop stress of 241.3 MPa. All test specimens were fabricated from 20% cold-worked Type 316 stainless steel tubes that were ribbed on the outer surface by mechanical grinding or electro-chemical etching. Test variables included specimen length and the presence or absence of weld-reinforcing end collars.
Date: November 1977
Creator: Yaggee, F. L.; Purohit, A.; Grajek, W. J. & Poeppel, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experimental Study of the Neutronics of the First Gas Cooled Fast Reactor Benchmark Assembly (GCFR Phase 1 Assembly)

Description: The Gas Cooled Fast Reactor (GCFR) Phase I Assembly is the first in a series of ZPR-9 critical assemblies designed to provide a reference set of reactor physics measurements in support of the 300 MW(e) GCFR Demonstration Plant designed by General Atomic Company. The Phase I Assembly was the first complete mockup of a GCFR core ever built. A set of basic reactor physics measurements were performed in the assembly to characterize the neutronics of the assembly and assess the impact of the neutron… more
Date: December 1976
Creator: Bhattacharyya, S. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Use of Krypton-85 for the Detection of Pinhole Failures in GCFR Cladding

Description: Radioactive krypton-85 is used as a tracer to detect pinhole failures in GCFR cladding. High-purity helium (99.99% pure) that contains 0.3 ppm krypton-85 is used to pressurize the tubular test specimens, and a Geiger-Mueller counter is used to detect the krypton-85 in the helium environmental gas as it leaves the test chamber. Under the least favorable conditions of temperature and specimen pressure, it is estimated that the smallest pinhole failure that could be detected within 60 sec would ha… more
Date: May 1976
Creator: Yaggee, F. L.; Purohit, A. & Poeppel, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Summary of Treat Experiments on Oxide Core-Disruptive Accidents

Description: A program of transient in-reactor experiments is being conducted by Argonne National Laboratory in the Transient Reactor Test (TREAT) facility to guide and support analyses of hypothetical core-disruptive accidents (HCDA) in liquid-metal fast breeder reactors (LMFBR). Test results provide data needed to establish the response of LMFBR cores to hypothetical accidents producing fuel failure, coolant boiling, and the movement of coolant, molten fuel, and molten cladding. These data include margins… more
Date: February 1979
Creator: Dickerman, Charles Edward; Rothman, Alan B.; Klickman, A. E.; Spencer, B. W. & DeVolpi, Alexander
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculations of Stresses in GCFR Cladding under Normal Operating Conditions

Description: A modified version of the LIFE-III code, LIFE-GCFR, and classical stress-analysis techniques have been used to calculate the stresses in the GCFR cladding under normal reactor operating conditions. Several types of loadings on the cladding that occur during normal operation have been considered. These include fuel-cladding mechanical interaction, thermal stresses induced by radial and axial temperature gradients, and swelling gradient-induced stresses. The combined and individual effects of the… more
Date: November 1979
Creator: Liu, Yung Y.; Hsieh, T. C. & Billone, Michael C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Postirradiation Examinations of Element G-3 from the GCFR F-1 Series of Mixed-Oxide Elements After Approximately 3 at.% Burnup

Description: Post-irradiation examinations were performed on element G-3, from the GCFR F-1 series of mixed-oxide elements, after 2.6 at. % burnup in EBR-II. The 20% cold-worked Type 316 stainless steel clad G-3 element was irradiated as an encapsulated element using a stainless steel thermal barrier to achieve peak cladding temperatures of 690 degrees C at a peak power of 14.4 kW/ft. The maximum diametral increase of the element was 0.2% ..delta..D/D₀. The volatile fission products were found just above th… more
Date: February 1977
Creator: Strain, R. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal Conductivity of the Helium-Argon System

Description: A semi-empirical relation for the thermal conductivity of helium-argon gas mixtures is suggested. The analyses used in support of the proposed conductivity relations are based on low-temperature (T < 800 degrees C) thermal conductivity data for helium, argon and helium-argon mixtures. The report is a compilation of available data and theories, and does not contain any new experimental results. With the approach presented here, one should be able to predict thermal conductivities of helium-argon… more
Date: February 1979
Creator: Purohit, A. & Moszynski, Jerzy R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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