Irradiation Testing Of Enrico Fermi Prototype Fuel Pins In The Cp 5 Reactor PDF Download

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Irradiation Testing of Enrico Fermi Prototype Fuel Pins in the CP-5 Reactor

Irradiation Testing of Enrico Fermi Prototype Fuel Pins in the CP-5 Reactor
Author: W. G. Blessing
Publisher:
Total Pages: 16
Release: 1960
Genre: Gamma rays
ISBN:

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Three Enrico Fermi prototype fuel pins have been irradiated in the CP-5 reactor to average burnups of 0.27, 0.58, and 0.85 per cent of the total atoms fissioned in the uranium -- 10 per cent by weight molybdenum fuel alloy. The purposes of the tests were to study the radiation stability of the full-size pins under environmental conditions similar to those expected in the Enrico Fermi Fast Breeder Reactor, and to verify the swelling-temperature-burnup relationships established in a previous capsule irradiation program conducted in the Materials Testing Reactor (MTR). Through correlation of diameter measurements, temperature, and postirradiation metallographic analysis, it is concluded that the radiation stability of the alloy is heavily dependent on the metallurgical condition of the material. The ? phase, stable above 1060 F, resists radiation more effectively than the ? + ? phases, which are thermally stable at temperatures less than 1045 F. Data from the CP-5 program suggest a more severe burnup limitation on this alloy than was previously concluded on the basis of the MTR results. The disparity is believed to be due to the influence of the fission-rate parameter on the microstructure of the material during irradiation. Fission events, if they occur with sufficient frequency, maintain the ? phase at temperatures below 1060 F. If the critical rate is not attained, the alloy will transform thermally in accordance with the uranium-molybdenum equilibrium diagram and the macroscopic temperature of the material.


SP-100 Fuel Pin Performance: Results from Irradiation Testing

SP-100 Fuel Pin Performance: Results from Irradiation Testing
Author:
Publisher:
Total Pages:
Release: 2005
Genre:
ISBN:

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A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF) reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pin are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the in-reactor fuel pin tests and presents the most recent irradiation data on the performance of wrought rhenium (Re) liner material and high density UN fuel at goal burnup of 6 atom percent (at. %). It also provides an overview of the significant variety of other fuel/liner/cladding combinations which were irradiated as part of this program and which may be of interest to more advanced efforts.


IRRADIATION OF PROTOTYPE CP-4 (EBR-I) REACTOR FUEL SLUGS IN THE CP-3' GOAT HOLE. Final Report of Metallurgy Division Program 6.1.1

IRRADIATION OF PROTOTYPE CP-4 (EBR-I) REACTOR FUEL SLUGS IN THE CP-3' GOAT HOLE. Final Report of Metallurgy Division Program 6.1.1
Author:
Publisher:
Total Pages:
Release: 1958
Genre:
ISBN:

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Experiments are described which studied the effect of irradiation upon small U/sup 235/ cylinders simulating in size those designed for thc initial CP-4 (EBR-I) fuel loading. Qualitative similarities between thermal cycling and irradiation effects were found, but none of the three types of inaterial tested were entirely dimensionally stable. (auth).


Analyses of Physics Specimens in Fuel Pins 1 and 2 Irradiated in the Dounreay Prototype Fast Reactor

Analyses of Physics Specimens in Fuel Pins 1 and 2 Irradiated in the Dounreay Prototype Fast Reactor
Author:
Publisher:
Total Pages: 65
Release: 1992
Genre:
ISBN:

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The United States and the United Kingdom have been engaged in a joint research program in which samples of fissile and fertile actinides have been incorporated into three separate fuel pins and irradiated in the Dounreay Prototype Fast Reactor in Scotland. The actinides in the second fuel pin were studied for fission-product decay, specifically to obtain absolute yields of 137Cs. Comparisons with calculated yields result in ratios of measured to calculated between 0.67 ({plus minus}0.05) and 1.09 ({plus minus}0.18). Plotting of experimental versus calculated values of 137Cs indicated that the assumed flux levels were some 5 to 20% overestimated. This flux level information will be useful in the forthcoming analysis of the last fuel pin, FP-4.


U.S. Power Reactors

U.S. Power Reactors
Author:
Publisher:
Total Pages: 236
Release: 1964
Genre: Nuclear energy
ISBN:

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