The design of the Prototype Fast Breeder Reactor

Chetal, S.C.; Balasubramaniyan, V.; Chellapandi, P.; Mohanakrishnan, P.; Puthiyavinayagam, P.; Pillai, C.; Raghupathy, S.; Shanmugham, T.K.; Pillai, C. Sivathanu

doi:10.1016/j.nucengdes.2005.09.025

Cited by 216 publications

(39 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The primary objective of the PFBR is to demonstrate techno-economic viability of fast breeder reactors on an industrial scale [5]. PFBR consists of three circuits namely Primary sodium, Secondary sodium and SteamWater circuits.…”

Section: Brief Description Of Pfbrmentioning

confidence: 99%

Role of animated Human Machine Interface in nuclear power plant

Bindu¹,

Gandhi²

2011

Int. j. simul. model.

View full text Add to dashboard Cite

The recent advances in Computer Science and Technology have revolutionized the way graphical user interfaces are used towards Human Machine Interface (HMI). The graphical user interface is so powerful, that the knowledge of a process or system can be transferred to plant personnel accurately and effectively within a short period of time. The techniques of animation can enhance the illusion of direct manipulation that many human computer interfaces strive to represent. This paper describes the role of human machine interface using animated information in Full Scope Replica type training simulator of Prototype Fast Breeder Reactor (PFBR). This paper covers general description of PFBR, the Full Scope Replica Simulator, the concept of simulation of plant dynamics, development of the animated core temperature distribution diagram and process flow diagram followed by its features. Also it covers how animated core temperature distribution and dynamic process flow diagrams are advantageous for operator training.

show abstract

Section: Brief Description Of Pfbrmentioning

confidence: 99%

Role of animated Human Machine Interface in nuclear power plant

Bindu¹,

Gandhi²

2011

Int. j. simul. model.

View full text Add to dashboard Cite

show abstract

“…Based on such assumptions, the DAE estimates that the maximum credible energy release in a CDA is 100 MegaJoules (MJ). 27 It then calculates that such a CDA leading to sodium leakage into the containment will result in a containment overpressure of 20 kPa.…”

Section: Safetymentioning

confidence: 99%

India and Fast Breeder Reactors

Ramana

2009

Science & Global Security

View full text Add to dashboard Cite

India has long pursued a fast breeder program, motivated in part by the availability of only poor quality uranium resources within the country. But progress so far has been disappointing, with only one test reactor having been constructed and having a chequered operating history. The larger Prototype Fast Breeder Reactor that is being constructed has a design that compromises safety and will produce expensive electricity, but could be used as a way to convert reactor-grade plutonium to weapon-grade plutonium. Projections offered by the nuclear establishment of fast growth of breeder reactors are methodologically flawed and based on very optimistic assumptions.

show abstract

“…Fast Breeder Test Reactor (FBTR) is in operation at Indira Gandhi Centre for Atomic Research at Kalpakkam since 1985. SFRs are commercially launched with the construction of 500 MWe PFBR (Chetal et al, 2006). PFBR is a sodium cooled, pool type reactor and two more similar reactors, FBR 1 & 2 of same capacity are planned to be constructed at Kalpakkam.…”

Section: Introductionmentioning

confidence: 99%