Over-pressure test on BARCOM pre-stressed concrete containment

Parmar, R. M.; Singh, Tej; Thangamani, I.; Trivedi, N.; Singh, Ram Kumar

doi:10.1016/j.nucengdes.2013.08.027

Cited by 40 publications

(14 citation statements)

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“…The crack opening displacement ( w ) during OPCs at peak pressures was observed to be in the range of 0.07 to 0.09 mm. The tensile strength of concrete ( f t ) used for BARCOM test model construction of M45 grade is 3.5 MPa . The fracture energy values of concrete for the three crack opening displacement values are expressed in Table in the range of 122 to 157 N/m and compare well with the reported G f (approximately 106‐136 N/m) obtained in the standard beam experiments with similar thickness of 188 mm for M45 grade of concrete as used in the BARCOM.…”

Section: Results Of Ocpmentioning

confidence: 99%

“…The milestone of stage III, with regard to the “first appearance of localized crack” was identified, in the discontinuity regions of MAL, EAL, and FMAL, through online monitoring of the inelastic strains using embedded VWSG and other strain gauges and confirmed with soap bubble test. The stage IV experiment is based on the evaluation of ultimate load capacity of BARCOM test model . The structural integrity and health of the containment model were continuously monitored during the over pressure tests at the different over‐pressures through the strain measurement at various El levels.…”

Section: Methodsmentioning

confidence: 99%

“…The present experimental program was organized by the Bhabha Atomic Research Centre (BARC), Trombay, India, for safety assessment of nuclear containment structures in case of the beyond design basis severe accidents. Under this program, an international round robin analysis was organized on BARC Containment (BARCOM) test model . The BARCOM test model of 1:4 size of pre‐stressed concrete inner containment structure of 540 MWe Pressurized Heavy Water Reactor of Tarapur Atomic Power Station Unit 3&4, as shown in Figure , was constructed in BARC experimental facilities at Tarapur.…”

Section: Introductionmentioning

confidence: 99%

“…However, for evaluating the fracture properties of concrete containments, in a quantitative manner with regard to crack formation, development of FPZ and crack propagation, localized full‐field strain mapping at the identified critical locations needs to be performed. In view of this, the DIC experimental technique was also implemented on BARCOM test model at Tarapur site by fixing four cameras at the critical locations identified through pre‐test analysis and further confirmed during initial over‐pressure tests . In the present study, DIC experiments have been used to map the full field of strain for visualizing the fracture growth, fracture propagation, and formation of FPZ on the BARCOM test model under over pressure conditions.…”

Section: Introductionmentioning

confidence: 99%

“…Under this program, an international round robin analysis was organized on BARC Containment (BARCOM) test model. [1][2][3] The BARCOM test model of 1:4 size of pre-stressed concrete inner containment Nomenclature: f t , tensile strength of concrete; w, crack opening displacement; w c , crack opening displacement at peak load; E, Young's modulus of elasticity of concrete; G f , fracture energy of concrete; P d , design pressure; σ, cohesive stress; ε, strain perpendicular to the crack growth structure of 540 MWe Pressurized Heavy Water Reactor of Tarapur Atomic Power Station Unit 3&4, as shown in Figure 1, was constructed in BARC experimental facilities at Tarapur. The design pressure (P d ) of the concrete containment model structure cast with M45 grade (diameter 12.376 m, nominal wall thickness 0.188 m, dome thickness of 0.164 m, and overall height of 15.75 m) is 0.1413 MPa.…”

Section: Introductionmentioning

confidence: 99%

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Structural integrity assessment of nuclear containment through fracture characterization

Trivedi

Singh

2018

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The paper deals with the study of structural response of partially cracked nuclear containment model structure in over pressurized condition with the simulated experiments conducted under severe accidents analysis program for Indian nuclear containment structures. In this research, the fracture characterization of concrete containment structure is also investigated through the over pressure experiments on the BARC Containment (BARCOM) test model structure, which represents 1:4 scale of the prototype 540 MWe Tarapur pre‐stressed nuclear containment structure. In addition to the surface‐type electrical resistance, strain gauges conventionally and commonly deployed for containment proof‐test and ultimate load capacity evaluation of containment models, embedded vibratory wire strain gauges (VWSGs), the digital image correlation (DIC) technique, and soap bubble tests are employed in this study. For fracture characterization, an optical crack profile (OCP) technique is developed through DIC full‐field experiment conducted at the identified critical locations with conventional strain gauges to evaluate the fracture energy and the characteristics of the fracture process zone of concrete containment model structure subjected to the over‐pressure condition for its performance assessment in the case of the beyond design basis accidents. The combination of conventional sensors and full‐field DIC deployed for the first time on the largest scale containment model along with the associated analysis is shown to be effective in fracture characterization and improved structural integrity assessment of the containment model.

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Section: Results Of Ocpmentioning

confidence: 99%

Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Structural integrity assessment of nuclear containment through fracture characterization

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2018

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Internal Pressure Monitoring in a Post-tensioned Containment Building Using Operational Vibration

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Structural integrity aspects of reactor safety

Vaze

2013

Sadhana

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The overall goal of nuclear power plant safety is to protect individuals, society and the environment from undue radiological hazard so that nuclear power production does not significantly add to the health risks to which individuals and society are already exposed. This paper addresses the safety principles followed during the design phase of life cycle of a nuclear power plant. The principles followed such as safety classification, design rules based on failure modes, detailed stress analysis, stress categorization, consideration of design basis events, failure probability, flaw tolerance, leak-before-break are described. Engineering structures always contain flaws, albeit of very small size. Fatigue and fracture are the two important failure modes affected by flaws. Thus flaw tolerance becomes very important. This is assessed by applying fracture mechanics principles. The R6 procedure, which is used for evaluation of structures containing flaws, has been incorporated in the software BARC-R6. Improvements by way of shell-nozzle junction pull-out, adoption of hot wire GTAW with narrow gap technique have been brought out. Post Fukushima incidence, resistance to seismic loading and containment design have assumed great importance. The paper describes these aspects in detail. Regulatory aspects of seismic design regarding siting, Seismic margin assessment, base isolation, retrofitting are the aspects covered under seismic design. Under the action of seismic loading, the piping in a nuclear power plant piping is vulnerable to a phenomenon called ratcheting. The process of seismic margin assessment and consideration of ratchetting has been backed up by a large experimental data. The experiments carried out on structures and piping components form a part of the paper.

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Over-pressure test on BARCOM pre-stressed concrete containment

Cited by 40 publications

References 1 publication

Structural integrity assessment of nuclear containment through fracture characterization

Structural integrity assessment of nuclear containment through fracture characterization

Internal Pressure Monitoring in a Post-tensioned Containment Building Using Operational Vibration

Structural integrity aspects of reactor safety

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