Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The high-temperature diametral expansion and rupture behavior of Zircaloy-4 fuel-cladding tubes have been investigated in vacuum and steam environments under transient-heating conditions that are of interest in hypothetical loss-of-coolant accident situations in light-water reactors. The effects of internal pressure, heating rate, axial constraint, and localized temperature nonuniformities in the cladding on the maximum circumferential strain have been determined for burst temperatures between approximately 650 and 1350°C.
High-temperature Deformation and Rupture Behavior of Internally-pressurized Zircaloy-4 Cladding in Vacuum and Steam Enivronments. [LOCA Conditions].
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The high-temperature diametral expansion and rupture behavior of Zircaloy-4 fuel-cladding tubes have been investigated in vacuum and steam environments under transient-heating conditions that are of interest in hypothetical loss-of-coolant accident situations in light-water reactors. The effects of internal pressure, heating rate, axial constraint, and localized temperature nonuniformities in the cladding on the maximum circumferential strain have been determined for burst temperatures between approximately 650 and 1350°C.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The high-temperature diametral expansion and rupture behavior of Zircaloy-4 fuel-cladding tubes have been investigated in vacuum and steam environments under transient-heating conditions that are of interest in hypothetical loss-of-coolant accident situations in light-water reactors. The effects of internal pressure, heating rate, axial constraint, and localized temperature nonuniformities in the cladding on the maximum circumferential strain have been determined for burst temperatures between approximately 650 and 1350°C.
Energy Research Abstracts
Energy Research Abstracts
Nuclear Safety
Proceedings of the Topical Meeting on Thermal Reactor Safety
Scientific and Technical Aerospace Reports
Boundary Effects on Zircaloy-4 Cladding Deformation in LOCA Simulation Tests. [PWR ; BWR].
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200
INIS Atomindex
Deformation and Rupture Behavior of Zircaloy Cladding Under Simulated Loss-of-Coolant Accident Conditions
Author: HM. Chung
Publisher:
ISBN:
Category : Deformation
Languages : en
Pages : 16
Book Description
Information on the diametral expansion and rupture characteristics of Zircaloy-4 cladding has been obtained in a vacuum environment over a wide range of internal pressures at several heating rates. The effect of axial constraint of the cladding, exerted by a mandrel that simulated the pellets in a fuel rod, on the relationship between the maximum circumferential strain and the burst temperature also was investigated. The circumferential strain for unconstrained cladding was significantly larger than for axially constrained tubes, particularly for burst temperatures below ~850°C, in which cladding remains essentially in the ?-phase. Three superplastic strain peaks have been identified, namely, at rupture temperatures of ~850, ~1050, and ~1220°C. In the case of complete axial restraint, the failure strains were not dependent on heating rate for burst temperatures above ~920°C; however the low-temperature (~850°C) strain peak increases and moves to lower temperatures as the heating rate decreases. The deformation data in this investigation also have been used to evaluate instability criteria proposed for thin-wall tubes under a biaxial stress state. The onset of plastic instability or local ballooning in the cladding has been defined in terms of the effective stress and strain during transient-heating conditions.
Publisher:
ISBN:
Category : Deformation
Languages : en
Pages : 16
Book Description
Information on the diametral expansion and rupture characteristics of Zircaloy-4 cladding has been obtained in a vacuum environment over a wide range of internal pressures at several heating rates. The effect of axial constraint of the cladding, exerted by a mandrel that simulated the pellets in a fuel rod, on the relationship between the maximum circumferential strain and the burst temperature also was investigated. The circumferential strain for unconstrained cladding was significantly larger than for axially constrained tubes, particularly for burst temperatures below ~850°C, in which cladding remains essentially in the ?-phase. Three superplastic strain peaks have been identified, namely, at rupture temperatures of ~850, ~1050, and ~1220°C. In the case of complete axial restraint, the failure strains were not dependent on heating rate for burst temperatures above ~920°C; however the low-temperature (~850°C) strain peak increases and moves to lower temperatures as the heating rate decreases. The deformation data in this investigation also have been used to evaluate instability criteria proposed for thin-wall tubes under a biaxial stress state. The onset of plastic instability or local ballooning in the cladding has been defined in terms of the effective stress and strain during transient-heating conditions.
Transactions of the American Nuclear Society
Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 692
Book Description
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 692
Book Description