Download or read book Effect of Hydrogen on the Oxygen Embrittlement of Beta Quenched Zircaloy 4 Fuel Cladding written by SL. Seiffert and published by . This book was released on 1982 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Zirconium in the Nuclear Industry written by D. Franklin and published by ASTM International. This book was released on 1982 with total page 516 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Zirconium in the Nuclear Industry written by and published by ASTM International. This book was released on with total page 490 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Proposed Criterion for the Oxygen Embrittlement of Zircaloy 4 Fuel Cladding written by A. Sawatzky and published by . This book was released on 1979 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Under the condition postulated for a loss-of-coolant accident (LOCA), Zircaloy-4 fuel cladding may experience a temperature transient during which it absorbs an appreciable amount of oxygen from the coolant. Theoretical models for predicting cladding behavior during loss-of-coolant (LOC) are being developed, but until the failure mechanisms can be clearly established, an empirical criterion must be employed.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1983 with total page 756 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Estimation of Conservatism of Present Embrittlement Criteria for Zircaloy Fuel Cladding Under LOCA written by T. Furuta and published by . This book was released on 1984 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: To estimate the degree of conservatism of the present embrittlement criteria, the following examinations have been conducted. Zircaloy-4 tubes were oxidized at temperatures ranging from 1173 to 1573 K, and then compressed at 373 K to determine the embrittlement due to oxygen absorption. The simulated Zircaloy-clad fuel rods were burst and oxidized in steam at temperatures within the range 1200 to 1500 K. The segment sectioned from each burst cladding was also compressed to determine the effect of hydrogen absorption on cladding embrittlement. The results obtained from these experiments have revealed that the additional embrittlement due to hydrogen absorption is found to be significant in burst cladding.
Download or read book Hydrogen Content Preoxidation and Cooling Scenario Effects on Post Quench Microstructure and Mechanical Properties of Zircaloy 4 and M5 Alloys in LOCA Conditions written by J. -C. Brachet and published by . This book was released on 2008 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: Previous papers pointed out the influence of long-term service exposures on the thermal-mechanical behavior of Zr alloys in LOCA conditions and, especially, the impact of in-service hydrogen pick-up on post-quench mechanical properties. Moreover, the oxide layer grown under in-service conditions was occasionally expected to have a protective effect against high temperature oxidation. Finally, the oxygen and hydrogen distributions within the prior-? layer appear as a key parameter with regard to the residual ductility of the alloy, especially as a function of the cooling scenario. The objective of the study presented here was to further investigate the influence of these parameters on the post-quench mechanical properties. Unirradiated Zircaloy-4 and M5® cladding tubes were consequently hydrided up to different concentration levels, then oxidized at high temperature (1000-1200°C) up to at least 10 % measured equivalent cladding reacted (ECR) and directly quenched to room temperature (RT). Ring compression tests (RCT), 3-point bending tests (3PBT) at RT and 135°C, as well as impact tests at RT were then performed to determine the evolution of the post-quench mechanical properties of Zircaloy-4 and M5® alloys with H content. Similarly, specimens preoxidized out-of-pile were also submitted to high temperature oxidation and direct quench, as well as to post-quench ring compression tests. Along with calculations of oxygen diffusion in the metal, results from those tests allowed us to estimate the assumed protective effect of the pretransient oxide layer. Finally, using specimens in the as-received condition or hydrided to typical end-of-life H contents, the effect of temperature history after oxidation at 1200°C was studied, i.e., at the end of the high temperature isothermal oxidation, samples were either submitted to direct quenching to RT or to slow cooling to different final quenching temperatures. It was thus demonstrated that the cooling scenario has a significant impact on the post-quench mechanical properties. All test samples were investigated by means of fractographic examinations to assess the type of failure mode. Moreover, a deep metallurgical analysis has been performed: SEM and image analysis were used for accurate phase thickness measurements, nuclear and electron microprobes for quantitative mapping of hydrogen and oxygen. It proved that the oxygen and hydrogen contents and their distribution in the prior-? layer have a first-order influence on the residual ductility. From all the results obtained on as-received and hydrided samples directly quenched from the oxidation temperature, it was then possible to derive a relationship between structural parameters, i.e., oxygen and hydrogen contents and thickness of the prior-? layer, and the post-quench impact properties at RT.
Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1983 with total page 1144 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Analysis of the Secondary Cladding Hydrogenation During the Quench LOCA Bundle Tests With Zircaloy 4 Claddings and Its Influence on the Cladding Embrittlement written by M. Walter and published by . This book was released on 2014 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: LOCA simulation tests were performed in the QUENCH facility of KIT on fuel rod bundle scale. The first two tests using Zircaloy-4 claddings, out of a series of six tests with different cladding alloys, were already performed. The test conditions and results are described. The secondary hydrogenation of the Zircaloy-4 cladding tubes was investigated by means of neutron imaging. In the cladding of the inner rods, hydrogen enriched bended bands were found. They are non-symmetrical to the tube axis. The bands are located at the position where significant inner oxidation ends. X-ray diffractometry (XRD) measurements show that the hydrogen remains at least partially in the zirconium lattice. The formation of the hydrogen enriched bands results in an embrittlement of the cladding tubes and in changes of the fracture mode in tensile tests. The micro-hardness of the cladding increases at the band position. The reasons of the formation of these hydrogen enriched bands and the dependence of its appearance on the temperature scenario are discussed.
Download or read book Nuclear Fuel Safety Criteria written by OECD Nuclear Energy Agency and published by OECD Publishing. This book was released on 2001 with total page 74 pages. Available in PDF, EPUB and Kindle. Book excerpt: Presents brief descriptions of 20 fuel-related safety criteria along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them.
Download or read book Hydrogen and Oxygen Distribution During Corrosion of Zirconium Alloy Nuclear Fuel Cladding written by Christopher Jones and published by . This book was released on 2020 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Materials written by and published by . This book was released on 1970 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Core Materials written by and published by . This book was released on 1964 with total page 316 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Review of Zircaloy 2 and Zircaloy 4 Properties Relevant to N S Savannah Reactor Design written by C. L. Whitmarsh and published by . This book was released on 1962 with total page 74 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Hydrogen Entry in Zircaloy 4 Fuel Cladding written by Jennifer Anne Jarvis and published by . This book was released on 2015 with total page 318 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion and hydrogen pickup of zirconium alloy fuel cladding in water cooled nuclear reactors are life-limiting phenomena for fuel. This thesis studies the fate of hydrogen liberated by waterside corrosion of Zircaloy-4 fuel cladding in Pressurized Water Reactors (PWRs): are the adsorbed protons incorporated into the oxide and eventually the metal, or are they evolved into molecular hydrogen and released into the coolant? Water chemistry modeling was used to understand effects of radiolysis and CRUD. Density functional theory (DFT) was used to investigate the role of oxidized Zr(Fe,Cr)2 second phase particles. Chemical potentials and the electron chemical potential were used to connect these two modeling efforts. A radiolysis model was developed for the primary loop of a PWR. Dose profiles accounting for fuel burnup, boron addition, axial power profiles, and a CRUD layer were produced. Dose rates to the bulk coolant increased by 21-22% with 12.5-75 pim thick CRUD layers. Radially-averaged core chemistry was compared to single-channel chemistry at individual fuel rods. Calculations showed that local chemistry was more oxidizing at high-power fuel and fuel with CRUD. Local hydrogen peroxide concentrations were up to 2.5 ppb higher than average levels of 5-8 ppb. Radiolysis results were used to compute chemical potentials and the corrosion potential. Marcus theory was applied to compare the band energies of oxides associated with Zircaloy-4 and the energy levels for proton reduction in PWR conditions. Hydrogen interactions with Cr203 and Fe203, both found in oxidized precipitates, were studied with DFT. Atomic adsorption of hydrogen was modeled on the Cr and Feterminated (0001) surfaces. Climbing Image-Nudged Elastic Band calculations were used to model the competing pathways of hydrogen migration into the subsurface and molecular hydrogen formation. A two-step mechanism for hydrogen recombination was identified consisting of: reduction of an adsorbed proton (H+) to a hydride ion (H-) and H2 formation from an adjacent adsorbed proton and hydride ion. Overall, results suggest that neither surface will be an easy entrance point for hydrogen ingress and that Cr203 is more likely to be involved in hydrogen evolution than the Fe203.
Download or read book Safety Aspects of Fuel Behaviour in Off normal and Accident Conditions written by OECD Nuclear Energy Agency and published by . This book was released on 1981 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1985 with total page 552 pages. Available in PDF, EPUB and Kindle. Book excerpt:
