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Postirradiation Examination Of A Low Enriched Usub 3isub 2 Al Fuel Element Manufactured And Irradiated At Batan Indonesia
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Book Synopsis Postirradiation Examination of a Low Enriched U[sub 3]i[sub 2]-Al Fuel Element Manufactured and Irradiated at Batan, Indonesia by :
Download or read book Postirradiation Examination of a Low Enriched U[sub 3]i[sub 2]-Al Fuel Element Manufactured and Irradiated at Batan, Indonesia written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The first low-enriched U[sub 3]Si[sub 2]-Al dispersion plate-type fuel element produced at the Nuclear Fuel Element Center, BATAN, Indonesia, was irradiated to a peak [sup 235]U burnup of 62%. Postirradiation examinations performed to data shows the irradiation behavior of this element to be similar to that of U[sub 3]Si[sub 2]-Al plate-type fuel produced and tested at other institutions. The main effect of irradiation on the fuel plates is a thickness increase of 30--40 [mu]m (2.5-3.0%). This thickness increase is almost entirely due to the formation of a corrosion layer (Boehmite). The contribution of fuel swelling to the thickness increase is rather small (less than 10 [mu]m) commensurate with the burnup of the fuel and the relatively moderate as-fabricated fuel volume fraction of 27% in the fuel meat.
Book Synopsis Postirradiation Examination of a Low Enriched U3Si2-Al Fuel Element Manufactured and Irradiated at Batan, Indonesia by :
Download or read book Postirradiation Examination of a Low Enriched U3Si2-Al Fuel Element Manufactured and Irradiated at Batan, Indonesia written by and published by . This book was released on 1994 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: The first low-enriched U3Si2-Al dispersion plate-type fuel element produced at the Nuclear Fuel Element Center, BATAN, Indonesia, was irradiated to a peak 235U burnup of 62%. Postirradiation examinations performed to data shows the irradiation behavior of this element to be similar to that of U3Si2-Al plate-type fuel produced and tested at other institutions. The main effect of irradiation on the fuel plates is a thickness increase of 30--40 [mu]m (2.5-3.0%). This thickness increase is almost entirely due to the formation of a corrosion layer (Boehmite). The contribution of fuel swelling to the thickness increase is rather small (less than 10 [mu]m) commensurate with the burnup of the fuel and the relatively moderate as-fabricated fuel volume fraction of 27% in the fuel meat.
Book Synopsis Post-irradiation Examination of U3Si{sub 1.6}-Al Dispersion Fuel Element LC04 by :
Download or read book Post-irradiation Examination of U3Si{sub 1.6}-Al Dispersion Fuel Element LC04 written by and published by . This book was released on 1993 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: A low-enrichment uranium (LEU) irradiation test (SIMONE project) was performed in the 45 MW Petten High-flux Reactor (HFR) as part of the Reduced Enrichment for Research and Test Reactor (RERTR) program. An LEU U3Si{sub 1.6}-Al dispersion fuel element with a fuel loading of 5.5 g cm−3 was irradiated and performed well to a total burnup of 66% and a peak burnup of 85%. The swelling behavior of the fuel was similar to that observed in previous U3Si(subscript x) irradiation experiments. The resulting fuel plate thickness increases and associated changes in coolant channel cross-sections were well within acceptable limits.
Book Synopsis Postirradiation Examination of High-U-loaded Low-enriched U3O, UAl2, and U3Si Test Fuel Plates by :
Download or read book Postirradiation Examination of High-U-loaded Low-enriched U3O, UAl2, and U3Si Test Fuel Plates written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The scope of this work is to present an evaluation of the postirradiation examination of the second set of high-U-loaded low-enriched U3O, UAl2 and U3Si miniature plates manufactured by the Comision Nacional de Energia Atomica (CNEA) of Argentina, and irradiated and examinated, within the framework of the Reduced Enrichment Research and Test Reactor (RERTR) Program, at Oak Ridge National Laboratory and Argonne National Laboratory. This paper includes fabrication details of the plates, their irradiation history and the results of postirradiation examination which are compared to those of the previous test and to present results from other laboratories participating in the RERTR Program. Postirradiation examination of these plates showed satisfactory poerformance for the oxides, aluminides and silicides (except for the highest-loaded U3Si plate) with the only indication of detrimental behavior during the slight bowing of some plates at about 80% burnup.
Book Synopsis Examination of U3Si2-Al Fuel Elements from the Oak Ridge Research Reactor by :
Download or read book Examination of U3Si2-Al Fuel Elements from the Oak Ridge Research Reactor written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The results of postirradiation examination of low-enriched U3Si2 fuel elements from the Oak Ridge Research Reactor are presented. The elements replaced standard high-enriched elements and were handled routinely except that the burnup of half the elements was extended beyond normal limits up to about 98% peak. The elements were manufactured by commercial fuel suppliers. The performance was completely satisfactory for all the elements.
Book Synopsis Post-Irradiation Examination of Appr Fuel Element Irradiation Program Specimens by :
Download or read book Post-Irradiation Examination of Appr Fuel Element Irradiation Program Specimens written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: APPR-type dispersion fuel element specimens containing temperature to respective burnups of approximately 50, 20, and 20% of uranium with no evidence of gross dimensional changes or loss of structural integrity. Blistering and/or core cracking has occurred when sections of 17.9 wt.% UO/sub 2/ specimens irradiated to burnups over 40% of uranium were subjected to post-irradiation annealing at 600 deg F for 24 hours. Post-irradiation core hardness measurements indicate that significant differences in irradiation damage exist between the various specimen types. These data indicate that the effects of the fabrication variables investigated in this program are as follows: The severity of irradiation damage in dispersion type fuel elements is inversely proportional to the UO/sub 2/ particle size of the fabricated plate. The particle size of the UO/ sub 2/ powder used in preparation of the initial core compact and the method of preparation of the UO/sub 2/ powders largely determine the final UO/sub 2/ particle size of roll-bonded, dispersion fuel plates. The particle size of the stainless steel powder used in the initial core mixture and the degree of cold reduction during final sizing of the fuel plate are apparently of relatively minor importance, at least for the systems investigated in this program. The severity of irradiation damage is directly proportional to the fuel concentration. Where an increased fuel loading is accompanied by an increase in the loading of the B/sub 4/C burnable poison to facilitate reactor control, the possibility of serious irradiation effects is increased to an even greater degree. (auth).
Book Synopsis Postirradiation Examination of U-Pu-Zr Fuel Elements Irradiated in EBR-II to 4.5 Atomic Percent Burnup by : W. F. Murphy
Download or read book Postirradiation Examination of U-Pu-Zr Fuel Elements Irradiated in EBR-II to 4.5 Atomic Percent Burnup written by W. F. Murphy and published by . This book was released on 1969 with total page 61 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Postirradiation Examination of a Mixed-oxide Fuel Element Irradiated to End- Of-life Conditions in Subassembly X106 in EBR-II. by :
Download or read book Postirradiation Examination of a Mixed-oxide Fuel Element Irradiated to End- Of-life Conditions in Subassembly X106 in EBR-II. written by and published by . This book was released on 1973 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Post-irradiation examination of a co-extruded u3si-zircaloy fuel element irradiated in a defected condition by : K. D. Cotnam
Download or read book Post-irradiation examination of a co-extruded u3si-zircaloy fuel element irradiated in a defected condition written by K. D. Cotnam and published by . This book was released on 1969 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Postirradiation Results and Evaluation of Helium-bonded Uranium--plutonium Carbide Fuel Elements Irradiated in EBR-II. Interim Report. [LMFBR]. by :
Download or read book Postirradiation Results and Evaluation of Helium-bonded Uranium--plutonium Carbide Fuel Elements Irradiated in EBR-II. Interim Report. [LMFBR]. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An evaluation was made of the performance of 74 helium-bonded uranium-plutonium carbide fuel elements that were irradiated in EBR-II at 38-96 kW/m to 2-12 at. percent burnup. Only 38 of these elements have completed postirradiation examination. The higher failure rate found in fuel elements which contained high-density (greater than 95 percent theoretical density) fuel than those which contained low-density (77-91 percent theoretical density) fuel was attributed to the limited ability of the high-density fuel to swell into the void space provided in the fuel element. Increasing cladding thickness and original fuel-cladding gap size were both found to influence the failure rates for elements containing low-density fuel. Lower cladding strain and higher fission-gas release were found in high-burnup fuel elements having smear densities of less than 81 percent. Fission-gas release was usually less than 5 percent for high-density fuel, but increased with burnup to a maximum of 37 percent in low-density fuel. Maximum carburization in elements attaining 5-10 at. percent burnup and clad in Types 304 or 316 stainless steel and Incoloy 800 ranged from 36-80 .mu.m and 38-52 .mu.m, respectively. Strontium and barium were the fission products most frequently found in contact with the cladding but no penetration of the cladding by uranium, plutonium, or fission products was observed.
Book Synopsis POST-IRRADIATION EXAMINATION OF THE GAIL III-B FUEL ELEMENT. by :
Download or read book POST-IRRADIATION EXAMINATION OF THE GAIL III-B FUEL ELEMENT. written by and published by . This book was released on 1964 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Testing of Full-sized, Reduced-enrichment Fuel Elements by :
Download or read book Irradiation Testing of Full-sized, Reduced-enrichment Fuel Elements written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The current status of the irradiation testing of full-sized, reduced-enrichment fuel elements and fuel rods under the US Reduced Enrichment Research and Test Reactor Program is reported. Being tested are UAl(subscript x)-Al, U3O-Al, U3Si2-Al, and U3Si-Al dispersion fuels and UZrH(subscript x) (TRIGA) fuel at uranium densities in the fuel meat ranging from 1.7 to 6.0 Mg/m3. Generally good performance has been experienced to date. Some preliminary results of postirradiation examinations are also included. A whole-core demonstration in the Oak Ridge Research Reactor is planned. Some details of this demonstration are provided.
Book Synopsis Postirradiation Examination and Evaluation of Peach Bottom Fuel Test Elements FTE-14 and FTE-15 by :
Download or read book Postirradiation Examination and Evaluation of Peach Bottom Fuel Test Elements FTE-14 and FTE-15 written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Peach Bottom fuel test elements FTE-14 and FTE-15 were companion nonaccelerated tests of fuel rods and fuel particles representative of the Large High-Temperature Gas-Cooled Reactor (LHTGR). The purpose of the tests was to broaden the data base of H-327 graphite and various fuel types; specifically, UO2, UC2, weak acid resin UC(subscript x)/O/sub y/, and several fertile fuel types were tested. The irradiation reached peak fuel temperatures of 1600°C volume- and time-averaged temperatures of 1300°C, and fast fluence exposures up to 2 x 1025 n/m2 (E> 29 fJ)/sub HTGR/. Experimental results were compared with predictions based on accelerated irradiation tests, postirradiation heating, and other Peach Bottom test elements to validate HTGR design codes. The nuclear design predictions were modified by measurements which allowed the verification of thermal design calculations and thermocouple readings.
Book Synopsis Post-Irradiation Evaluation of a Plate-Type UO$sub 2$ Fuel Element by :
Download or read book Post-Irradiation Evaluation of a Plate-Type UO$sub 2$ Fuel Element written by and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The premature failure of fuel Element M22, which had six compartments of 0.100-in.-thick, 96% TD UO/sub 2/ + 6 wt% ZrO/sub 2/ fuel, was attributed to the large irradiation-induced solid volume swelling of the UO/sub 2/ fuels. This volume swelling was the result of incomplete homogenization during fabrication of the mixed and sintered U/sup E/O/sub 2/ and U/sup N/O/sub 2/ fuel s in Element M22. In addition, heavy hydriding of the Ni-free Zircaloy-2 cladding occurred in the relatively hot areas adjacent to the fuel and to a lesser extent at the external cladding surfaces. By postulation, H/sub 2/ was apparently formed by the radiolytic decomposition of water entrapped between fuel and cladding after formation of the initial cladding defect, and was absorbed by the cladding so rapidly that it could not diffuse adequately down the thermal gradient to the cold side of the cladding. The corrosion behavior of the cladding was as expected and did not contribute to the hydriding. Analysis of the CR-X-3 loop operating history indicates that no abnormal conditions external to Element M22 existed in the loop other than U from inpile intentionally defected fuel elements. (auth).
Book Synopsis The Post-irradiation Examination of the D7 (XPR-2) Fuel Element by : L.J. Hankart
Download or read book The Post-irradiation Examination of the D7 (XPR-2) Fuel Element written by L.J. Hankart and published by . This book was released on 1971 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Postirradiation Examination and Evaluation of Peach Bottom Fuel Test Element FTE-6 by :
Download or read book Postirradiation Examination and Evaluation of Peach Bottom Fuel Test Element FTE-6 written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fuel test element FTE-6 was irradiated in the Peach Bottom high-temperature gas-cooled reactor (HTGR) for 645 equivalent full power days. Four fuel varieties, contained in H-327 graphite bodies, were tested. A primary result of this test has been to demonstrate acceptable performance even with calculated high stresses in the graphite bodies. Heterogeneous fuel loadings in the element caused local power peaking and azimuthal power variations, deforming the graphite fuel bodies and thereby causing bowing nearly five times as large as the diametral clearance within the sleeve. The axial stresses resulting from interference between the fuel bodies and sleeve were estimated to have reached 45% of the ultimate material strength at the end of the irradiation. Residual stresses from differential contraction within the fuel body resulted in probable in-plane stress levels of 130% of the material strength at the end-of-life shutdown and of up to 150% of the strength at shutdown during the irradiation cycle. The high in-plane stresses are local peaks at the corners of a sharp notch in the element, which may account for the stresses failing to cause damage. The lack of observable damage, however, indicates that the methods and data used for stress analysis give results that are either fairly accurate or conservative.
Book Synopsis Postirradiation Examination Results for the Irradiation Effects Scoping Test 1 by :
Download or read book Postirradiation Examination Results for the Irradiation Effects Scoping Test 1 written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A zircaloy-clad UO/sub 2/ fuel rod was operated above its critical heat flux within the in-pile test loop of the Power Burst Facility and later examined in the hot cells. The results of the postirradiation examinations are presented in this report. A Zr-UO/sub 2/ reaction at the fuel-cladding interface embrittled nearly as much of the cladding wall thickness as the Zr-water reaction on the exterior. Data on both the internal and external reactions, and cladding and fuel microstructures, are presented. Cladding embrittlement and rod failure are compared with several rod fragmentation criteria, and conclusions concerning fuel rod failure propagation in a power reactor system are made.
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