Published January 2021 | Version v1
Journal article Metadata-only

Threshold stress intensity factor of delayed hydride cracking in irradiated and unirradiated zircaloy-4 cladding

Creators

  • 1. Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 34057, Rep. of (Korea, Republic of)
  • 2. Studsvik Nuclear AB, Nykoping 61182 (Sweden)

Description

The delayed hydride cracking (DHC) is becoming important because of its extended long-term dry storage and lower dry storage temperature than expected. However, it remains difficult to predict the DHC behavior of PWR spent fuel cladding due to the limited data of KIH (i.e., threshold stress intensity factor), especially for irradiated claddings. In this regard, the KIH for unirradiated and irradiated (49.641 GWd/tU) Zircaloy-4 claddings were experimentally measured using a pin-loaded-tension (PLT) technique and described by investigating the affected parameters. In addition, the results were compared with estimations from our previous studies. From the analysis, DHC is not expected to be a major concern during the predicted conditions of dry storage.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2020.152596

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2020.152596;
PII
S0022311520312046;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
543
Journal Page Range
vp.
ISSN
0022-3115
CODEN
JNUMAM

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
54020024
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Descriptors DEI
CLADDING; DRY STORAGE; HYDRIDES; IRRADIATION; PWR TYPE REACTORS; SPENT FUELS; STRESS INTENSITY FACTORS; ZIRCALOY 4
Descriptors DEC
ALLOYS; ALLOY-ZR98SN-4; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HYDROGEN COMPOUNDS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; STORAGE; SURFACE COATING; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Copyright
Copyright (c) 2020 Elsevier B.V. All rights reserved.