Log in

Relevant bibliographies by topics / Prototype Fast Breeder Reactor (PFBR)

Contents

Journal articles

Academic literature on the topic 'Prototype Fast Breeder Reactor (PFBR)'

Author: Grafiati

Published: 4 June 2021

Last updated: 11 June 2025

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Prototype Fast Breeder Reactor (PFBR).'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Journal articles on the topic "Prototype Fast Breeder Reactor (PFBR)"

1

Anuraj, Vijayan, Goverapet Srinivasan, and Kunhiraman Devan. "Stability characteristics of the 500 mw Indian PFBR." Nuclear Technology and Radiation Protection 30, no. 2 (2015): 113–23. http://dx.doi.org/10.2298/ntrp1502113a.

Full text

Abstract:

After the successful operation of the fast breeder test reactor for over two decades, India is now nearing the completion of a 500 MW (electrical) prototype fast breeder reactor. This commercial scale power reactor is a sodium-cooled, pool-type, mixed-oxide fuelled fast reactor. The stability characteristics of the reactor are an important safety aspect to be studied. In the present work, linear stability of the prototype fast breeder reactor analysis is carried out using the transfer function method, while the stability of the system is checked via the Nyquist criteria. For the completeness o

APA, Harvard, Vancouver, ISO, and other styles

2

Kumar, Prabhat. "Welding and Fabrication of Stainless Steel Equipment for 500MWe Prototype Fast Breeder Reactor." Advanced Materials Research 794 (September 2013): 305–15. http://dx.doi.org/10.4028/www.scientific.net/amr.794.305.

Full text

Abstract:

Austenitic stainless steel is the major structural material for the primary and secondary sodium systems (except for the steam generators) for the currently operating and planned fast reactors all over the world. The boundaries of sodium systems of Prototype Fast Breeder Reactor (PFBR) is designed so as to have an extremely low probability of leakage, rapidly propagating failure and gross rupture under the static & dynamic loads expected during various operating conditions.The degradation of material properties (e.g. effect of sodium, temperature and irradiation), transients, residual stre

APA, Harvard, Vancouver, ISO, and other styles

3

Azhagarason, B., N. Mahendran, Tarun Kumar Mitra, and Prabhat Kumar. "Technological Challenges in Manufacturing of over Dimensional Stainless Steel Components of PFBR." Advanced Materials Research 794 (September 2013): 186–93. http://dx.doi.org/10.4028/www.scientific.net/amr.794.186.

Full text

Abstract:

Prototype Fast Breeder Reactor (PFBR) is liquid sodium cooled, pool type nuclear reactor with generating capacity of 1250 MWt / 500MWe. Reactor assembly consists of many large dimensional components made of special grade austenitic stainless steel material. Safety vessel and Main vessel are torispherical dished end vessels with overall height of 12.8 m and 13.4/12.9 m diameter with thickness ranging from 20 to 40 mm. Vessels approx. 111 / 135 MT with running weld length of 500 & 540 m. Inner vessel and thermal baffles are the internals of reactor assembly made of SS 316LN. Forming of dishe

APA, Harvard, Vancouver, ISO, and other styles

4

Balaguru, S., K. Deenadayalan, Murali Vela, and P. Chellapandi. "Influence of Welding Speed over Dilution for Circular Grid Plate Hardfaced with Colmonoy-5." Applied Mechanics and Materials 565 (June 2014): 53–58. http://dx.doi.org/10.4028/www.scientific.net/amm.565.53.

Full text

Abstract:

Colmonoy is a nickel based alloy hardfaced with SS-316 used in Prototype Fast Breeder Reactors (PFBR) to avoid self-welding and galling between nuclear reactor and grid plate. Colmonoy is coated on the base metal –SS 316 by Plasma transfer arc welding. Due to thermal cycling that exist in reactors de-bonding between colmonoy and base metal occurs which may lead to catastrophic failure of the Prototype fast breeder reactor. Hence, estimation of the fatigue life period of hardfaced colmonoy is mandatory. Before that, finding optimum parameters which influences fusion, weld strength, composition

APA, Harvard, Vancouver, ISO, and other styles

5

Dutta, N. G. "Helium Leak Detection of Vessels in Fuel Transfer Cell (FTC) of Prototype Fast Breeder Reactor (PFBR)." Journal of Physics: Conference Series 390 (November 5, 2012): 012080. http://dx.doi.org/10.1088/1742-6596/390/1/012080.

Full text

APA, Harvard, Vancouver, ISO, and other styles

6

Rangasamy, R. G., and Prabhat Kumar. "Quality Management during Manufacturing of High Tempertaure Thin Walled Austenitic Stainless Steel Sodium Tanks of Prototype Fast Breeder Reactor." Advanced Materials Research 794 (September 2013): 507–13. http://dx.doi.org/10.4028/www.scientific.net/amr.794.507.

Full text

Abstract:

Austenitic stainless steels are the major material of construction for the fast breeder reactors in view of their adequate high temperature mechanical properties, compatibility with liquid sodium coolant, good weldability, availability of design data and above all the fairly vast and satisfactory experience in the use of these steels for high temperature service. All the Nuclear Steam Supply System (NSSS) components of FBR are thin walled structure and require manufacture to very close tolerances under nuclear clean conditions. As a result of high temperature operation and thin wall constructi

APA, Harvard, Vancouver, ISO, and other styles

7

Balaguru, S., K. Saranraj, Murali Vela, and P. Chellapandi. "Variation in Residual Stresses due to Thermal Cycling Induced on the Hardfaced Grid Plate in PFBR." Applied Mechanics and Materials 591 (July 2014): 98–102. http://dx.doi.org/10.4028/www.scientific.net/amm.591.98.

Full text

Abstract:

In sodium cooled fast breeder reactors, the high operating temperature necessitates hard facing of grid plate to avoid galling and to reduce the wear loss of the base material . Nickel-base cobalt-free alloy called Colmonoy-5 has been chosen as the hard facing material for the Prototype Fast Breeder Reactor (PFBR) grid plate. The grid plate (GP) which is a critical component made of 316 LN SS that holds the core subassemblies are hard faced, to prevent galling and also to minimize wear caused by subassembly insertion/removal and erosion due to high sodium velocity at 670 K. Thermal cycling of

APA, Harvard, Vancouver, ISO, and other styles

8

Perumalsamy, G., P. Visweswaran, D. Jagadishan, S. Joseph Winston, and S. Murugan. "Optimisation of helical geometry of inspection probe for steam generator tubes of the PFBR." Insight - Non-Destructive Testing and Condition Monitoring 63, no. 10 (2021): 585–91. http://dx.doi.org/10.1784/insi.2021.63.10.585.

Full text

Abstract:

The steam generator (SG) tubes of the prototype fast breeder reactor (PFBR) located in Kalpakkam, India, need to be periodically inspected using the remote field eddy current (RFEC) technique. During the pre-service inspection of the SG tubes, it was found that the RFEC probes experienced frequent mechanical breakages. To avoid these failures, changes in the existing structural design of the RFEC probe were required. A helical groove design was proposed to obtain a smooth transition in the variation of stress across the probe during the inspection. It was difficult to calculate the flexural st

APA, Harvard, Vancouver, ISO, and other styles

9

Balaguru, S., K. Saranraj, Murali Vela, and P. Chellapandi. "Evaluation of Stress Intensity Factor of 316 SS LN Circular Grid Plate Hardfaced with Colmonoy 5 for Various Loads." Applied Mechanics and Materials 431 (October 2013): 173–76. http://dx.doi.org/10.4028/www.scientific.net/amm.431.173.

Full text

Abstract:

In sodium cooled fast breeder reactors, the high operating temperature necessitates hardfacing of grid plate to avoid galling of the base material. Nickel based cobalt-free alloy called Colmonoy-5 has been chosen as the hard facing material for the Prototype Fast Breeder Reactor (PFBR) grid plate. The grid plate (GP) which is a critical component made of SS316 that holds the core subassemblies are hard faced, to prevent galling caused by subassembly insertion/removal and erosion due to high sodium velocity at 670 K. Colmonoy 5 was hardfaced on circular grid plate along the annular groove by Pl

APA, Harvard, Vancouver, ISO, and other styles

10

Kumar Krovvidi, S. C. S. P., C. S. Surendran, N. Chakraborthy, et al. "Experience with Material Combinations for Sliding Applications in PFBR In-Vessel Fuel Handling Machine." Advanced Materials Research 794 (September 2013): 705–13. http://dx.doi.org/10.4028/www.scientific.net/amr.794.705.

Full text

Abstract:

Prototype Fast breeder Reactor (PFBR) is a pool type reactor of 500 MW(e) capacity using mixed oxides of Uranium and Plutonium as fuel and liquid sodium as coolant, which is currently under advanced stage of construction at Kalpakkam. In-Vessel handling of the core subassemblies (SA) is carried out by an offset arm type machine called Transfer Arm (TA). Different types of material combinations are utilized for various sliding pairs used in the machine for various motions. Criteria for the selection of these material combinations are decided by the compatibility of the respective machine elemen

APA, Harvard, Vancouver, ISO, and other styles

More sources

We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!