Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
SWELLING OF URANIUM. Report
Author: Metallographic Observations of Swelling in Uranium
Author: T. K. BierleinPublisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 128
Book Description
Metallographic Observations of Swelling in Uranium
Author: T. K. BierleinUranium Swelling in N-Reactor (PT-NR-4, Sup. A, Report No. 1).
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 15
Book Description
Five monitor columns, containing some pre-irradiation weighed inner and outer fuel elements, were discharged under authorization of PT-NR-4, Sup A at tube average exposures in the range from 1554 to 1631 MWD/T. Uranium swelling values have been calculated from post-irradiation weight measurements and these swelling values have been compared with those swelling values obtained in the KER loop tests. There is acceptable agreement between KER and NPR results for swelling of inner uranium; there is acceptable agreement for outer fuel elements at higher exposures but ends-of-the-column elements (i.e. low-exposure values) are not in agreement. The current swelling values have been extrapolated to determine the tube-average exposure that will result in outer clad strains of one percent. At this conservative value of clad strain, one can predict entirely adequate performance of outer fuel elements to tube average exposures of 2200 MWD/T and inner fuel elements to 2700 MWD/T tube average exposure. Elements that will soon be discharged at tube average exposures ranging from 1900 to 2100 MWD/T, can be evaluated for swelling during the next outage and a much better prediction can be made on the relation of exposure vs swelling and hence exposure vs fuel element integrity. The continuing objective of this production test remains as the determination of fuel element performance vs exposure.
Final Report
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
A single swelling capsule was irradiated in DIR reactor as a test of the operation and design of a series of similar capsules to be charged later in a large scale uranium swelling experiment. The ratio of measured to calculated uranium temperature increased from 0.7 during the first two-thirds of the irradiation to 1.08 during the last one-third. Most of this change can be accounted for by a flux shift toward the rear of the reactor during the last one-third of the irradiation. Because of this flux shift it was impossible to determine an accurate temperature correction factor to be applied to the full scale test to follow. Radiometallurgy revealed an asymmetric radial temperature distribution in the fuel. Capsule tests showed that this asymmetry was caused by in complete NaK coverage of the rod; Capsule design change will prevent this.
Calculations of the Rate of Swelling of Gas Bubbles in Uranium
Author: Atomic Energy Research Establishment (Harwell, England)Publisher:
ISBN:
Category :
Languages : en
Pages : 9
Book Description
Китайское ремесло в XVI-XVIII веках
Author: Calculation of Radiation Induced Swelling of Uranium Mononitride Using the Digital Computer Program CYGRO 2
Author: Nuclear Regulatory Commission Issuances
Author: U.S. Nuclear Regulatory CommissionPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 950
Book Description
Swelling Behavior of KSE-5 Fuel Elements ; KER Test K-1-22
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 4
Book Description
Production Test IP-544-A authorized the irradiation testing of coextruded Zr-2 jacketed, single tube, thick walled, 1.6 percent enriched tubular elements (KSE-5's) in KER loops 1 and 2 to evaluate swelling behavior at high uranium temperatures. This PT was intended to permit the evaluation of uranium swelling at N-reactor environmental conditions but at considerably higher uranium temperatures than those occurring in N-reactor fuel. Evaluation of the fuel performances at the authorized maximum fuel temperatures in the 550--600 C temperature range is essential in the design and analysis of single tube fuel elements for use in N-reactor. The test was subsequently supplemented to authorize the irradiation of uranium fuel containing up to 3000 ppm alloying agents for the evaluation of swelling behavior at the high uranium temperatures. This report describes the swelling behavior of a charge of 8 KSE-5 fuel elements irradiated in KER loop 1 to appproximately 2500 MWD/T as Test K-1-22. KER Test K-1-22 is similar (except for exposure level) to KER Test K-2-21 in which a charge of 8 KSE-5 fuel elements were irradiated to 1500 MWD/T. In both tests the charges consisted of 4 KSE-5's containing uranium with low iron and silicon additions (N-reactor fuel composition) and 4 KSE-5's containing uranium with 400 ppm iron and 800 ppm aluminum. The objective of both tests was to obtain comparative swelling performance data for the two fuel compositions under identical irradiation conditions.