A Study of the Structural Integrity of the Core Support Structure of a Fast Breeder Reactor

1992 ◽  
Vol 100 (1) ◽  
pp. 1-12
Author(s):  
Masahiro Ueta ◽  
Masakazu Ichimiya ◽  
Hiroshi Hirayama ◽  
Masayuki Asano ◽  
Hisaaki Ikeuchi ◽  
...  
Keyword(s):  
Structural Integrity ◽  
Fast Breeder Reactor ◽  
Support Structure ◽  
The Core

Nuclear Instrumentation Systems in Prototype Fast Breeder Reactor

2004 ◽  
Author(s):  
P. M. Vijayakumaran ◽  
C. P. Nagaraj ◽  
C. Paramasivan Pillai ◽  
R. Ramakrishnan ◽  
M. Sivaramakrishna
Keyword(s):  
Neutron Flux ◽  
Early Warning System ◽  
Warning System ◽  
Radiation Monitoring ◽  
Fast Breeder Reactor ◽  
Delayed Neutrons ◽  
The Core ◽  
Flux Monitoring ◽  
Nuclear Instrumentation ◽  
Fission Chambers

The nuclear instrumentation systems of the Prototype Fast Breeder Reactor (PFBR) primarily comprise of global Neutron Flux Monitoring, Failed Fuel Detection & Location, Radiation Monitoring and Post-Accident Monitoring. High temperature fission chambers are provided at in-vessel locations for monitoring neutron flux. Failed fuel detection and location is by monitoring the cover gas for fission gases and primary sodium for delayed neutrons. Signals of the core monitoring detectors are used to initiate SCRAM to protect the reactor from various postulated initiating events. Radiation levels in all potentially radioactive areas are monitored to act as an early warning system to keep the release of radioactivity to the environment and exposure to personnel well below the permissible limits. Fission Chambers and Gamma Ionisation Chambers are located in the reactor vault concrete for monitoring the neutron flux and gamma radiation levels during and after an accident.

Sodium-Free Level Fluctuations: Concern on Structural Integrity for the Pool-Type Sodium-Cooled Fast Breeder Reactor

2017 ◽  
pp. 407-417
Author(s):  
V. R. Chandan Reddy ◽  
R. Suresh Kumar ◽  
Anil Kumar Sharma ◽  
K. Velusamy ◽  
P. Selvaraj
Keyword(s):  
Structural Integrity ◽  
Fast Breeder Reactor ◽  
Free Level ◽  
Pool Type

Analysis of Sodium Fire in the Containment Building of Prototype Fast Breeder Reactor Under the Scenario of Core Disruptive Accident

2006 ◽  
Author(s):  
P. M. Rao ◽  
N. Kasinathan ◽  
S. E. Kannan
Keyword(s):  
Structural Integrity ◽  
Peak Pressure ◽  
Safety Issue ◽  
Pressure Rise ◽  
Pool Fire ◽  
Mode Analysis ◽  
Fast Breeder Reactor ◽  
Reactor Assembly ◽  
Computer Codes ◽  
Breeder Reactors

The potential for sodium release to reactor containment building from reactor assembly during Core Disruptive Accident (CDA) in Fast Breeder Reactors (FBR) is an important safety issue with reference to the structural integrity of Reactor Containment Building (RCB). For Prototype Fast Breeder Reactor (PFBR), the estimated sodium release under a CDA of 100 MJ energy release is 350 kg. The ejected sodium reacts easily with air in RCB and causes temperature and pressure rise in the RCB. For estimating the severe thermal consequences in RCB, different modes of sodium fires like pool and spray fires were analyzed by using SOFIRE–II and NACOM sodium fire computer codes. Effects of important parameters like amount of sodium, area of pool, containment air volume and oxygen concentration have been investigated. A peak pressure rise of 7.32 kPa is predicted by SOFIRE II code for 350 kg sodium pool fire in 86,000 m3 RCB volume. Under sodium release as spray followed by unburnt sodium as pool fire mode analysis, the estimated pressure rise is 5.85 kPa in the RCB. In the mode of instantaneous combustion of sodium, the estimated peak pressure rise is 13 kPa.

Load-Carrying Characteristics of Foam Core and Joint Geometry in Sandwich Structures

2020 ◽  
Author(s):  
Jonas W. Ringsberg
Keyword(s):  
Structural Integrity ◽  
Side Wall ◽  
Core Material ◽  
Fe Model ◽  
Foam Core ◽  
Stress Concentrations ◽  
Production Time ◽  
Composite Sandwich ◽  
The Core ◽  
Load Carrying

Abstract Composite sandwich ships have laminated joints that contribute to a significant part of the ship’s weight. Their construction requires an extensive number of man-hours. There is great potential for weight and production-time-reduction through alternative joint designs. According to class rules, one is not allowed to benefit from the load-carrying capability of the core, i.e. the strength characteristics of the core shall be disregarded and geometry at the joint location is disregarded as well. The objective of the current investigation was to investigate the possibility of constructing a joint where the load-carrying capability of the foam core is accounted for, leading to a reduction in weight and production time. One specific joint in a 23 m composite sandwich catamaran was selected for study — a side wall-wet deck T-joint. This joint is considered to be crucial for the structural integrity of the current vessel. A global finite element (FE) model of the catamaran was designed and analysed in ANSYS. The loads and boundary conditions were applied to the global model according to DNV GL’s HSLC rules. Two local FE models of the joints (2D and 3D) were utilized for a parametric analysis with respect to structure response (stress concentrations and compliance with failure and fracture criteria). Finally, the results and conclusions from the study show the possibilities and advantages of incorporating the foam core material as a load-carrying member in joint design without compromising safety.

A Holistic Approach to Structural Integrity Methods Supporting Graphite Core Assessments

2008 ◽  
Author(s):  
C. D. Elcoate ◽  
G. M. Davis ◽  
L. E. Easterbrook
Keyword(s):  
Structural Integrity ◽  
Reactor Core ◽  
Holistic Approach ◽  
Normal Operation ◽  
Transient Conditions ◽  
The Core ◽  
Inspection Strategy ◽  
Safety Case ◽  
Core Components ◽  
Stress And Deformation

An understanding of the behaviour of radially-keyed graphite cores and the internal stress and deformation of individual core components under normal operation and transient conditions is essential in assessing core geometry, component integrity, inspection strategy and consequently core integrity. When assessing graphite core integrity an in-depth understanding of the broad range of material and physical behaviours of the core during steady-state, transients and fault conditions is essential. This paper describes recent advances in the approach developed to assess Magnox reactor core structural integrity, which is one of the legs comprising a graphite core safety case, the other legs being inspection, monitoring and consequences.

Analytical Electron Microscopy of Neutron-Irradiated Reactor Alloys

1982 ◽  
Vol 40 ◽  
pp. 594-597
Author(s):  
L. E. Thomas
Keyword(s):  
Analytical Electron Microscopy ◽  
Structural Steels ◽  
Core Region ◽  
Fast Breeder Reactor ◽  
X Ray ◽  
The Core ◽  
Analytical Electron ◽  
Segregation Of Alloying Elements ◽  
Edx Microanalysis ◽  
High Neutron

Exposure to the high neutron fluxes and temperatures from 400 to 650°C in the core region of a fast breeder reactor profoundly alters the microstructure and properties of structural steels and superalloys. The development of irradiation-induced voids, dislocations and precipitates, as well as segregation of alloying elements on a microscopic scale has been related to macroscopic swelling, creep, hardening and embrittlement which occur during prolonged exposures in reactor. Microanalytical studies using TEM/STEM methods, primarily energy dispersive X-ray (EDX) microanalysis, have greatly aided our understanding of alloy behavior under irradiation.

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