Results 41 to 50 of about 167,510,152 (115)

Modelling and Simulation of Reactor Fuel Cladding under Loss-of-Coolant Accident Conditions [PDF]

open access: yes, 2011
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors.
Massih, Ali R,   +5 more
core   +1 more source

Multi-layer Coated Cladding Behaviour during Loss of Coolant Accident

open access: yes, 2023
Při havárii LOCA je palivové pokrytí vystavené vysokým teplotám a vnitřnímu přetlaku, což může vést k nafukování proutku a jeho následnému přetržení nebo blokování průtoku chladiva z havarijních systémů.
Michaela Svatošová
core  

Estimating Loss-of-Coolant Accident Frequencies for the Standardized Plant Analysis Risk Models [PDF]

open access: yes, 2008
The U.S. Nuclear Regulatory Commission maintains a set of risk models covering the U.S. commercial nuclear power plants. These standardized plant analysis risk (SPAR) models include several loss-of-coolant accident (LOCA) initiating events such as small (
Eide, S. A.   +2 more
core  

Analysis of a small break loss-of-coolant accident of pressurized water reactor by APROS

open access: yes, 1995
The purpose of this paper is to study the capability of APROS (Advanced PROcess Simulator) code to simulate the real plant thermal-hydraulic transient of a Small Break Loss-Of-Coolant Accident (SBLOCA) of Loss-Of-Fluid Test (LOFT) facility. The LOFT is a
Porkholm, Kari   +2 more
core   +2 more sources

Data for: Deep neural network based prediction of burst parameters for Zircaloy-4 fuel cladding during loss-of-coolant accident

open access: yes
This is database of single-tube burst tests conducted on unirradiated Zircaloy-4 cladding tubes under simulated loss-of-coolant transients. This database was used for developing Deep neural network model to prediction burst parameters for Zircaloy-4 fuel
SUMAN, S
core   +1 more source

Summary of accident investigations /

open access: yes, 1972
Title from cover.Mode of access: Internet.Continued by: Analysis & summary of accident investigations.Continues: Analysis and summary of accident ...
United States. Bureau of Motor Carrier Safety.
core  

Analysis of Loss of Coolant Accident in MTR Pool Type Research Reactors

open access: yes, 2005
During the operation lifetime of a Nuclear Research Reactors, the frequency of occurrence of LOCA event is expected to be very seldom. In case of MTR pool type research reactor, a loss of coolant accident could occur as consequence of a rupture of a
BOUSBIA SALAH A   +3 more
core  

Description of steam condensation phenomena during the loss-of-coolant accident. [BWR] [PDF]

open access: yes, 1981
Study of results from the full scale multivent pressure suppression experiment conducted by the GKSS Laboratory has developed an improved understanding of the dynamic, oscillatory steam condensation events and related loading functions which occur during
McCauley, E.W.   +5 more
core  

A method for modeling under-expanded jets [PDF]

open access: yes, 2013
textIn nuclear power plants, a pipe break in the cooling line releases a jet that damages other equipment in containment, and is known as a loss of coolant accident (LOCA). This report specifically focuses on boiling water reactor (BWR) applications as a
Day, Julia Katherine
core  

Transient Heat Conduction in Cryogenic Current Cables Following a Loss-of-Coolant Accident

open access: yes, 1977
The current supply cables of large superconducting magnet systems are cooled with an axial stream of cold helium vapor. If the flow of coolant is suddenly interrupted the current cables may overheat and burn up causing extensive damage to the entire ...
A. Bejan
core   +1 more source

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