Effect of Hydrogen on the Oxygen Embrittlement of Beta-Quenched Zircaloy-4 Fuel Cladding

Effect of Hydrogen on the Oxygen Embrittlement of Beta-Quenched Zircaloy-4 Fuel Cladding PDF Author: SL. Seiffert
Publisher:
ISBN:
Category : Embrittlement
Languages : en
Pages : 26

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Effect of Hydrogen on the Oxygen Embrittlement of Beta-Quenched Zircaloy-4 Fuel Cladding

Effect of Hydrogen on the Oxygen Embrittlement of Beta-Quenched Zircaloy-4 Fuel Cladding PDF Author: SL. Seiffert
Publisher:
ISBN:
Category : Embrittlement
Languages : en
Pages : 26

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Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: D. Franklin
Publisher: ASTM International
ISBN: 9780803107540
Category : Business & Economics
Languages : en
Pages : 516

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Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 490

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A Proposed Criterion for the Oxygen Embrittlement of Zircaloy-4 Fuel Cladding

A Proposed Criterion for the Oxygen Embrittlement of Zircaloy-4 Fuel Cladding PDF Author: A. Sawatzky
Publisher:
ISBN:
Category : Embrittlement
Languages : en
Pages : 18

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Book Description
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.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 756

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Estimation of Conservatism of Present Embrittlement Criteria for Zircaloy Fuel Cladding Under LOCA

Estimation of Conservatism of Present Embrittlement Criteria for Zircaloy Fuel Cladding Under LOCA PDF Author: T. Furuta
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 13

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Book Description
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.

ERDA Energy Research Abstracts

ERDA Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1144

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Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5® Alloys in LOCA Conditions

Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5® Alloys in LOCA Conditions PDF Author: J. -C. Brachet
Publisher:
ISBN:
Category : Brittleness
Languages : en
Pages : 28

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Book Description
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.

Analysis of the Secondary Cladding Hydrogenation During the Quench-LOCA Bundle Tests With Zircaloy-4 Claddings and Its Influence on the Cladding Embrittlement

Analysis of the Secondary Cladding Hydrogenation During the Quench-LOCA Bundle Tests With Zircaloy-4 Claddings and Its Influence on the Cladding Embrittlement PDF Author: M. Walter
Publisher:
ISBN:
Category : Hydrogen embrittlement
Languages : en
Pages : 20

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Book Description
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.

Nuclear Fuel Safety Criteria

Nuclear Fuel Safety Criteria PDF Author: OECD Nuclear Energy Agency
Publisher: OECD Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 74

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Book Description
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.