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Determinations of the temperature of terminal solid solubility in dissolution and precipitation of hydrogen/deuterium in irradiated Zircaloy-4

Abstract

The proposed plan is an approach to the metallurgical consequences of the high neutron fluencies (10''2''2 n/cm''2) on the hydrogen behavior in zirconium based alloys, based on the significance of the microstructural behavior of the high burn up fuel claddings during the dry storage period. The studies are focused on Zircaloy-4, concerning to two processes: Neutron irradiation damage; Hydrogen pick up. The Zircaloy-4 was taken from cooling channels of the PHWR Atucha 1. These components remained more than 10 years in service, reaching neutron fluencies up to 10''2''2 n/cm''2. In the last recent years, measurements of the hydride dissolution temperatures have shown that hydrogen solubility is affected by the neutron irradiation, increasing it respect to the unirradiated Zircaloy solubility. In addition, in this material the amorphization/dissolution of the second phase particles (SPPs) was observed, being proposed an interaction between the hydrogen atoms, the SPPs and the irradiation defects as a possible explanation of the observed behavior. For the present case, attention will be focused on the hydride precipitation process, since it is strongly related with delay hydrogen cracking initiation, a problem of direct concern for the dry storage. The goal of the present proposal is to make an approach to  More>>
Authors:
Vizcaino, P [1] 
  1. CNEA-CONICET, Centro Atomico Ezeiza (Argentina)
Publication Date:
Jul 01, 2012
Product Type:
Technical Report
Report Number:
IAEA-TECDOC-1680
Resource Relation:
Related Information: In: Spent Fuel Performance Assessment and Research. Final Report of a Coordinated Research Project (SPAR-II)| 161 p.
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; AMORPHOUS STATE; ANNEALING; ATUCHA-1 REACTOR; BURNUP; CALORIMETRY; CLADDING; COOLING; CRACKING; DAMAGE; DAMAGING NEUTRON FLUENCE; DEUTERIUM; DISSOLUTION; DRY STORAGE; HYDRIDES; HYDROGEN; MICROSTRUCTURE; NEUTRONS; PRECIPITATION; RADIATION EFFECTS; SOLUBILITY; TEMPERATURE RANGE 0400-1000 K; TRANSMISSION ELECTRON MICROSCOPY; X-RAY DIFFRACTION; ZIRCALOY 4
OSTI ID:
22028545
Research Organizations:
International Atomic Energy Agency, Nuclear Fuel Cycle and Materials Section, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Contract Number:
SPAR-II CRP Agreement No. 14377
Other Identifying Numbers:
Other: ISBN 978-92-0-130810-8; ISSN 1011-4289; TRN: XA12S0152116815
Availability:
Available from INIS in electronic form. Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/TE_1680_web.pdf; Enquiries should be addressed to IAEA, Marketing and Sales Unit, Publishing Section, E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books
Submitting Site:
INIS
Size:
page(s) 125-126
Announcement Date:
Jan 18, 2013

Citation Formats

Vizcaino, P. Determinations of the temperature of terminal solid solubility in dissolution and precipitation of hydrogen/deuterium in irradiated Zircaloy-4. IAEA: N. p., 2012. Web.
Vizcaino, P. Determinations of the temperature of terminal solid solubility in dissolution and precipitation of hydrogen/deuterium in irradiated Zircaloy-4. IAEA.
Vizcaino, P. 2012. "Determinations of the temperature of terminal solid solubility in dissolution and precipitation of hydrogen/deuterium in irradiated Zircaloy-4." IAEA.
@misc{etde_22028545,
title = {Determinations of the temperature of terminal solid solubility in dissolution and precipitation of hydrogen/deuterium in irradiated Zircaloy-4}
author = {Vizcaino, P}
abstractNote = {The proposed plan is an approach to the metallurgical consequences of the high neutron fluencies (10''2''2 n/cm''2) on the hydrogen behavior in zirconium based alloys, based on the significance of the microstructural behavior of the high burn up fuel claddings during the dry storage period. The studies are focused on Zircaloy-4, concerning to two processes: Neutron irradiation damage; Hydrogen pick up. The Zircaloy-4 was taken from cooling channels of the PHWR Atucha 1. These components remained more than 10 years in service, reaching neutron fluencies up to 10''2''2 n/cm''2. In the last recent years, measurements of the hydride dissolution temperatures have shown that hydrogen solubility is affected by the neutron irradiation, increasing it respect to the unirradiated Zircaloy solubility. In addition, in this material the amorphization/dissolution of the second phase particles (SPPs) was observed, being proposed an interaction between the hydrogen atoms, the SPPs and the irradiation defects as a possible explanation of the observed behavior. For the present case, attention will be focused on the hydride precipitation process, since it is strongly related with delay hydrogen cracking initiation, a problem of direct concern for the dry storage. The goal of the present proposal is to make an approach to the source of the observed effect, applying several specific techniques as differential scanning calorimetry (DSC), high resolution x-ray diffraction and transmission electron microscopy. The objectives can be divided as follows: Determination of the temperatures of terminal solid solubility in dissolution (TTSSd) and in precipitation (TTSSp) in high fluency irradiated Zircaloy-4, reproducing the temperatures at which the Zircaloy fuel claddings remain during dry storage by an annealing program during the DSC experiments; Observations by optical and transmission electron microscopy of the hydride distribution before (as received material) and after high temperature annealings, trying to get deepener on the cause of the observed effects.}
place = {IAEA}
year = {2012}
month = {Jul}
}