Download or read book Irradiation Creep Deformation of Modified 316 and 15Cr 20Ni Base Austenitic Fuel Elements Irradiated in FFTF written by S. Ukai and published by . This book was released on 2001 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep of modified 316 (PNC316) and 15Cr-20Ni base austenitic stainless steels was determined using the diametral change of the fuel pins, which were irradiated under the fission gas pressurized condition in FFTF to a peak displacement damage of 107 dpa in PNC316 and 120 dpa in 15Cr-20Ni base. The creep compliance B0 and creep-swelling coupling coefficient D were found to be 1.1 to 3.0 x 10-6 MPa-1 dpa-1 and up to 1.3 x 10-2 MPa-1 for instantaneous volumetric swelling rate, respectively. Those are almost the same level as those derived using the pressurized tubes irradiated in FFTF-MOTA. D values tend to decrease and disappear with developing void swelling.

Download or read book Effects of Radiation on Materials written by Stan T. Rosinski and published by ASTM International. This book was released on 2001 with total page 879 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by Martin L. Grossbeck and published by ASTM International. This book was released on 2004 with total page 767 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field

Download or read book Journal of Nuclear Science and Technology written by and published by . This book was released on 2008 with total page 686 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes English language abstracts from Japanese articles in Nihon Genshiryoku Gakkai Shi (Journal of the Atomic Energy Society of Japan)

Download or read book Comparison of Irradiation Creep and Swelling of an Austenitic Alloy Irradiated in FFTF and PFR written by FA. Garner and published by . This book was released on 1999 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Comparative irradiation of identically constructed creep tubes in the Fast Flux Test Facility (FFTF) and the Prototypic Fast Reactor (PFR) shows that differences in irradiation conditions arising from both reactor operation and the design of the irradiation vehicle can have a significant impact on the void swelling and irradiation creep of austenitic stainless steels. In spite of these differences, the derived creep coefficients fall within the range of previously observed values for 316 SS.

Download or read book Reanalysis of Swelling and Irradiation Creep Data on 316 Type Stainless Steels Irradiated in the FFTF and Ph nix Fast Reactors written by MB. Toloczko and published by . This book was released on 2000 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: In comparing results of irradiation creep experiments conducted by researchers in France and those by researchers at Pacific Northwest National Laboratory in the United States, quite different values for the creep-swelling coupling coefficient were reported. The differing coefficients complicated the understanding of the growing data base on irradiation creep. However, upon careful consideration, the French and US results showed key differences in experimental technique and analysis. The French and US irradiation creep experiments were conducted with several important differences that were initially thought to be of little consequence. One difference was related to whether stress-free swelling or stress-enhanced swelling was measured and used in calculating the creep strains. Inspection of irradiation creep results published by the French also showed their technique for extracting the creep-swelling coupling coefficient was different than that used by the present authors. In an effort to better understand the origin of the differing creep coefficients, data from the French and US experiments was reanalyzed taking into account these differences. In performing this reanalysis, completely consistent results were obtained.

Download or read book Reduction of Irradiation Induced Creep and Swelling in AISI 316 by Compositional Modifications written by JF. Bates and published by . This book was released on 1981 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: Studies involving high fluence irradiations of compositionally modified AISI 316 stainless steel have demonstrated that the irradiation-induced creep and swelling of this alloy can be modified through a selective choice of alloying elements. Irradiation-induced swelling of specimens irradiated to fluences of 7 to 12 x 1022 neutrons/cm2 (E > 0.1 MeV) is strongly influenced by the concentration of alpha-stabilizing elements such as silicon and molybdenum. Relative minima and maxima in swelling versus composition diagrams are shown to exist. Irradiation-induced creep strain of AISI 316 is, in general, reduced by the same elements which reduce irradiation-induced swelling. It was found that the compositional dependence of both swelling and creep in this alloy system can be described through a description of the screening of dislocation strain fields. Compositional modifications which increase the mobility of the screening agents or allow the formation of more effective screening agents will decrease the swelling and irradiation creep. This screening results in a decrease in the interstitial-dislocation bias, which results in lower swelling and in-reactor creep.

Download or read book Irradiation Creep and Swelling of Various Austenitic Alloys Irradiated in PFR and FFTF written by and published by . This book was released on 1996 with total page 251 pages. Available in PDF, EPUB and Kindle. Book excerpt: In order to use data from surrogate neutron spectra for fusion applications, it is necessary to analyze the impact of environmental differences on property development. This is of particular importance in the study of irradiation creep and its interactions with void swelling, especially with respect to the difficulty of separation of creep strains from various non-creep strains. As part of an on-going creep data rescue and analysis effort, the current study focuses on comparative irradiations conducted on identical gas-pressurized tubes produced and constructed in the United States from austenitic steels (20% CW 316 and 20% CW D9), but irradiated in either the Prototype Fast Reactor (PFR) in the United Kingdom or the Fast Flux Test Facility in the United States. In PFR, Demountable Subassemblies (DMSA) serving as heat pipes were used without active temperature control. In FFTF the specimens were irradiated with active ("°5C) temperature control. Whereas the FFTF irradiations involved a series of successive side-by-side irradiation, measurement and reinsertion of the same series of tubes, the PFR experiment utilized simultaneous irradiation at two axial positions in the heat pipe to achieve different fluences at different flux levels. The smaller size of the DMSA also necessitated a separation of the tubes at a given flux level into two groups (low-stress and high-stress) at slightly different axial positions, where the flux between the two groups varied d"0%. Of particular interest in this study was the potential impact of the two types of separation on the derivation of creep coefficients.

Download or read book Irradiation Effects on the Microstructure on Properties of Metals written by ASTM International Symposium on Effects of Radiation on Structural Materials and published by ASTM International. This book was released on 1976 with total page 502 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effect of Irradiation Environment of Fast Reactor s Fuel Elements on Void Swelling in P Ti Modified 316 Stainless Steel written by I. Yamagata and published by . This book was released on 2001 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The difference in swelling behavior of P, Ti-modified 316 stainless steel (PNC316) between sample irradiation using material irradiation vehicle (e.g. FFTF/MOTA) and fuel assembly irradiation in FBR was investigated. From the evaluation of the dose dependence in the swelling of PNC316, it is clearly shown that swelling of claddings irradiated by fuel assemblies occurred earlier than the swelling of samples irradiated by material irradiation vehicle in the range of irradiation temperatures from 723K to 823K. The microstructural evolution of the claddings irradiated by fuel assemblies, which is represented by void formation, should be mainly affected by the irradiation environments: irradiation temperature history, temperature gradient within the thickness of the claddings, and by the primary and secondary stresses within the cladding during irradiation.

Download or read book Determination of Creep Compliance and Creep swelling Coupling Coefficients for Neutron irradiated Titanium modified Stainless Steel at 00 C written by and published by . This book was released on 1991 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep data from FFTF-MOTA at ∼400°C were analyzed for nine 20% cold-worked titanium-modified type 316 stainless steels, each of which exhibits a different duration for the transient regime of swelling. One of these steels was the fusion prime candidate alloy designated PCA. The others were various developmental breeder reactor heats. The analysis was based on the assumption that the B0 + DS creep model applies to these steels at this temperature. This assumption was found to be valid. A creep-swelling coupling coefficient of D ≈ 0.6 × 10−2 MPa−1 was found for all steels that had developed a significant level of swelling. This result is in excellent agreement with the results of earlier studies conducted in EBR-II using annealed AISI 304L and also 10% and 20% cold-worked AISI 316 stainless steels. There appears to be some enhancement of swelling by stress, contradicting an important assumption in the analysis and leading to an apparent but misleading nonlinearity of creep with respect to stress.

Download or read book Influence of Irradiation on the Creep Fatigue Behavior of Several Austenitic Stainless Steels and Incoloy 800 at 700 C written by JM. Beeston and published by . This book was released on 1973 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results from elevated temperature-strain controlled fatigue and constant-strain-rate tensile tests conducted on specimens of stainless steel Types 304, 304L (titanium modified), 316, as well as Incoloy 800 are reported. Specimens were irradiated to fluences of 0.4 to 5 x 1022 n/cm2, E>0.1 MeV at 700 to 750 C (1292 to 1382 F), while the postirradiation test temperature was maintained at 700 C. Reductions in tensile ductility and fatigue life occurred, with reductions in fatigue life ranging from factors of approximately 1.5 to 2.5 for the stainless steels and up to 35 for Incoloy 800 in comparison with the thermal controls. Comparisons are made between actual irradiated fatigue behavior and predictions based on several semi-empirical methods using irradiated tensile data. These methods generally provided good estimates of the irradiated fatigue behavior of these materials. Introducing tensile hold times into the fatigue cycles of irradiated and unirradiated Type 316 stainless steel resulted in substantial reductions in the fatigue life of this material. However, for tensile hold times in excess of 0.1 h a tendency towards saturation of the hold-time effect was found in both the irradiated and unirradiated material. Creep and fatigue damage for Type 316 stainless was determined and summed linearly. This total damage was found to be a function of strain range, duration of tensile hold time, and irradiation condition for Type 316 stainless steel.

Download or read book Irradiation Creep in Type 316 Stainless Steel and US PCA with Fusion Reactor He written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep was investigated in type 316 stainless steel (316 SS) and US Fusion Program PCA using a tailored spectrum of the Oak Ridge Research Reactor in order to achieve a He/dpa value characteristic of a fusion reactor first wall. Pressurized tubes with stresses of 20 to 470 MPa were irradiated at temperatures of 330, 400, 500, and 600°C. It was found that irradiation creep was independent of temperature in this range and varied linearly with stress at low stresses, but the stress exponent increased to 1.3 and 1.8 for 316 SS and PCA, respectively, at higher stresses. Specimens of PCA irradiated in the ORR and having helium levels up to 200 appM experienced a 3 to 10 times higher creep rate than similar specimens irradiated in the FFTF and having helium levels below 20 appM. The higher creep rates are attributed to either a lower flux or the presence of helium. A mechanism involving interstitial helium-enhanced climb is proposed. 17 refs.

Download or read book Irradiation Creep and Stress Affected Swelling in Austenitic Stainless Steel 16Cr 15Ni 3Mo Nb B Irradiated in the BN 350 Reactor written by AN. Vorobjev and published by . This book was released on 2000 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep and void swelling are important damage processes for stainless steels when subjected to neutron irradiation at elevated temperatures. To date, most published data of this type have been derived from steels prepared by various Western nations and Japan. This paper describes the results of an experiment involving irradiation of gas-pressurized tubes constructed from Russian niobium-stabilized austenitic steel EP-172 of type 16Cr-15Ni-3Mo-Nb doped with boron. The tubes were irradiated in the lowenrichment zone of the BN-350 fast reactor to three doses of 20, 45 and 60 dpa at temperatures in the range of 480-520°C.

Download or read book Solute Addition Effect for Fe 15Cr 20Ni Austenitic Steels Irradiated in Joyo written by I. Yamagata and published by . This book was released on 2004 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The relationship between the addition of minor element and the swelling behavior was investigated using six heats of Fe-15Cr-20Ni austenitic model alloys and a PNC 1520 steel irradiated at 480, 570, 620 and 700°C in the Joyo to doses of 20-56 dpa. Phosphorus and boron suppressed the appearance of swelling for these experimental irradiation conditions. Additions of titanium and niobium were effective for suppression of swelling at low temperature, below 570°C. Radiation -induced precipitation is an important factor for controlling the appearance of swelling. The radiation-produced phases in PNC1520 during neutron irradiation are classified into four groups: (1) Frank loops with Ti aggregation on the habit plane, (2) Rod-type precipitates of Fe2P, (3) Large bulk-type precipitates of M23C6, and (4) Blocky-type precipitates of MC with Ti, M6C, Ni-Laves and TiP. The phosphide precipitates strongly suppressed swelling in the low temperature regime as cavity formation started only after phosphide dissolved during neutron irradiation.

Download or read book Determination of Creep Compliance and Creep swelling Coupling Coefficients for Neutron irradiated Titanium modified Stainless Steel at 400 Degree C written by and published by . This book was released on 1991 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep data from FFTF-MOTA at (approximately)400°C were analyzed for nine 20% cold-worked titanium-modified type 316 stainless steels, each of which exhibits a different duration for the transient regime of swelling. One of these steels was the fusion prime candidate alloy designated PCA. The others were various developmental breeder reactor heats. The analysis was based on the assumption that the B0 + DS creep model applies to these steels at this temperature. This assumption was found to be valid. A creep-swelling coupling coefficient of D (almost equal to) 0.6 x 10−2 MPa−1 was found for all steels that had developed a significant level of swelling. This result is in excellent agreement with the results of earlier studies conducted in EBR-II using annealed AISI 304L and also 10% and 20% cold-worked AISI 316 stainless steels. There appears to be some enhancement of swelling by stress, contradicting an important assumption in the analysis and leading to an apparent but misleading nonlinearity of creep with respect to stress.