High-temperature Deformation and Rupture Behavior of Internally-pressurized Zircaloy-4 Cladding in Vacuum and Steam Enivronments. [LOCA Conditions]. PDF Download

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High-temperature Deformation and Rupture Behavior of Internally-pressurized Zircaloy-4 Cladding in Vacuum and Steam Enivronments. [LOCA Conditions].

High-temperature Deformation and Rupture Behavior of Internally-pressurized Zircaloy-4 Cladding in Vacuum and Steam Enivronments. [LOCA Conditions]. PDF 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].

High-temperature Deformation and Rupture Behavior of Internally-pressurized Zircaloy-4 Cladding in Vacuum and Steam Enivronments. [LOCA Conditions]. PDF 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.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 548

Book Description


Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 688

Book Description


Nuclear Safety

Nuclear Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 864

Book Description


Proceedings of the Topical Meeting on Thermal Reactor Safety

Proceedings of the Topical Meeting on Thermal Reactor Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 830

Book Description


Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports PDF Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 990

Book Description


Boundary Effects on Zircaloy-4 Cladding Deformation in LOCA Simulation Tests. [PWR ; BWR].

Boundary Effects on Zircaloy-4 Cladding Deformation in LOCA Simulation Tests. [PWR ; BWR]. PDF 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

INIS Atomindex

INIS Atomindex PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 944

Book Description


Deformation and Rupture Behavior of Zircaloy Cladding Under Simulated Loss-of-Coolant Accident Conditions

Deformation and Rupture Behavior of Zircaloy Cladding Under Simulated Loss-of-Coolant Accident Conditions PDF 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.

Transactions of the American Nuclear Society

Transactions of the American Nuclear Society PDF Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 692

Book Description