• No results found

Pressurized Water Reactor

Experimental Validation of the Material Properties of the Inner Containment of the Pressurized Water Reactor (EPR Type)

Experimental Validation of the Material Properties of the Inner Containment of the Pressurized Water Reactor (EPR Type)

... The inner containment is a pre-stressed concrete structure, designed to bear loads from internal hazards, such as overpressure and high temperature resulting from Loss of Coolant Accident (LOCA). The leak tightness ...

6

Structural Analysis and Evaluation on the Containment Structure of the Pressurized Water Reactor Plants with Consideration of the Aging Effects

Structural Analysis and Evaluation on the Containment Structure of the Pressurized Water Reactor Plants with Consideration of the Aging Effects

... with pressurized water reactor (PWR) is very critical and the last physical barrier and it is irreplaceable equipment, such that the containment design service life is directly related to the nuclear ...

10

Impact Analysis of a Spacer Grid Assembly of Dual Cooled Fuel for Pressurized Water Reactor

Impact Analysis of a Spacer Grid Assembly of Dual Cooled Fuel for Pressurized Water Reactor

... The dynamic impact analysis was performed to evaluate the impact characteristics of the spacer grid assembly of dual cooled fuel for pressurized water reactor. The analysis was performed for the full ...

7

Prognostic modelling utilizing a high fidelity pressurized water reactor simulator

Prognostic modelling utilizing a high fidelity pressurized water reactor simulator

... Abstract— Within power generation, ageing assets and an emphasis on more efficient operation of power systems and improved maintenance decision methods has led to a growing focus on asset prognostics. The main challenge ...

7

Simulation of the static mechanical behaviour of a pressurized water reactor fuel assembly

Simulation of the static mechanical behaviour of a pressurized water reactor fuel assembly

... The nuclear fuel assembly is one of the major components of a pressurized water reactor (PWR). During the service in the core, it has to withstand to irradiation, high temperatures, mechanical loads ...

7

IASCC Susceptibility On Core Baffle Barrel Structure In Pressurized Water Reactor

IASCC Susceptibility On Core Baffle Barrel Structure In Pressurized Water Reactor

... The reactor vessel (RV) internal components in pressurized water reactor (PWR) are very important structure to support reactor ...

9

Neutron-gamma flux and dose calculations in a Pressurized Water Reactor (PWR)

Neutron-gamma flux and dose calculations in a Pressurized Water Reactor (PWR)

... Tihange-I is a Pressurized Water Reactor (PWR), producing a nominal electric power of 900 MW. Following the first divergence of the core in 1975, start-up physics tests were performed. In this work, ...

8

Impact and benefit of the Pre-stressing System on the Inner Containment of the Pressurized Water Reactor (EPR Type)

Impact and benefit of the Pre-stressing System on the Inner Containment of the Pressurized Water Reactor (EPR Type)

... The advantages of the bonded pre-stressing system of the pressurized water reactor (EPR TM type) inner containment have been demonstrated. The alignment of tendons, the state of concrete compression ...

7

Analysis of Neutronics and Thermal Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PWR)

Analysis of Neutronics and Thermal Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PWR)

... In this study, fuel pin optimization is performed for Pressurized Water Reactor. The results are specifically dependent on design specification and design criteria. The pitch to fuel pin radius ratio ...

10

Passive Cooldown Performance of Integral Pressurized Water Reactor

Passive Cooldown Performance of Integral Pressurized Water Reactor

... Most of the primary circuit components of an integral pressurized water reactor (IPWR) are housed within a single reactor pressure vessel (RPV). This layout can provide the optimum ...

5

Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Pressurized Water Reactor Standard Core Loading Benchmark Problem

Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Pressurized Water Reactor Standard Core Loading Benchmark Problem

... This paper documents radiation transport calculation results using the Westinghouse-developed RApid Parallel Transport Of Radiation – Multiple 3-D Geometries (RAPTOR-M3G) code version 2.0 [1] with Oak Ridge National ...

9

Steam Generator Liquid Mass as a Control Input for the Movement of the Feed Control Valve in a Pressurized Water Reactor

Steam Generator Liquid Mass as a Control Input for the Movement of the Feed Control Valve in a Pressurized Water Reactor

... Choi et al. (S2) states that replacing the current analog control loop for the steam generator water level with digital computer control expands the range of possible solutions. Their work shows that the digital ...

129

HFR Informations for Users  Survey of high flux facilities in the HFR Petten, selected for boiling water and pressurized water reactor (BWR and PWR) materials testing  EUR 4639

HFR Informations for Users Survey of high flux facilities in the HFR Petten, selected for boiling water and pressurized water reactor (BWR and PWR) materials testing EUR 4639

... 50.— The present report gives a brief survey of the high flux reactor a t the Petten establishment of the joint research establisment, its principal facilities and corresponding irradiat[r] ...

48

Development   of a Generalized Flaw Distribution as Input to the Re-evaluation of the   Technical Basis for U.S. Pressurized Thermal Shock Regulation of Pressurized   Water Reactor Vessels

Development of a Generalized Flaw Distribution as Input to the Re-evaluation of the Technical Basis for U.S. Pressurized Thermal Shock Regulation of Pressurized Water Reactor Vessels

... The formal use of expert judgment (sometimes referred to as expert opinion) has been extensively applied to a number of major studies in the nuclear probabilistic risk assessment ar[r] ...

8

The Use of Acoustic Monitoring   to Manage Concrete Structures in the Nuclear Industry (O380)

The Use of Acoustic Monitoring to Manage Concrete Structures in the Nuclear Industry (O380)

... The PCCP model structure discussed in this section of the paper was constructed by Sandia National Laboratories in New Mexico in cooperation with the Nuclear Power Engineering Corporation (NUPEC) of Japan and the US ...

15

Predictive Study of CAP1400 Core Barrel Flow-induced Vibration-Part1: Turbulence-induced Forcing Function

Predictive Study of CAP1400 Core Barrel Flow-induced Vibration-Part1: Turbulence-induced Forcing Function

... a pressurized water reactor is a cylindrical barrel, containing the fuel assemblies inside, hanging from the vessel ...the reactor internals, the vibration of the core barrel has always been ...

10

Cracking Susceptibility of Irradiated Stainless Steels in a Simulated PWR Environment

Cracking Susceptibility of Irradiated Stainless Steels in a Simulated PWR Environment

... Cracking susceptibility of irradiated Types 316, 316LN and 347 stainless steels (SS) were evaluated with slow-strain-rate tensile (SSRT) tests in a simulated pressurized water reactor (PWR) ...

11

Risk-Informed Assessment   of Degraded Containment Structures (D455)

Risk-Informed Assessment of Degraded Containment Structures (D455)

... containment structures to prevent radiation release during a severe accident. A research program is underway to quantify the effects of various types of containment degradation in a risk-informed manner. In this paper, ...

8

Influence of Thermal Ageing and Specimen Size on Fracture Toughness of Z3CN20 09M Casting Duplex Stainless Steels

Influence of Thermal Ageing and Specimen Size on Fracture Toughness of Z3CN20 09M Casting Duplex Stainless Steels

... the pressurized water reactor (PWR) nuclear power plant to manufacture the primary pressure boundary components, such as pipes, valves and fl anges, in view of their excellent mechanical properties, ...

5

Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation

Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation

... light water reactor severe ...on Pressurized Water Reactor (PWR) MOX fuel behaviour submitted to severe accident conditions and related FP speciation; going further in the understanding ...

10

Show all 10000 documents...

Related subjects