No abstract available

[en] A test section is presented for analysis of water flow on LMFBR geometries. The prototype of the fuel element consists of 7 tube rods with spacer wires. Studies are forecasted on axial flow to obtain experimental assembly friction factor, and the swirl-flow as well. The project also intend to install electrical resistors for thermal gradient studies. (L.C.J.A.)

No abstract available

[en] The demand for energy in India is sure to rise year after year. Every possible energy source needs to be utilized to its fullest potential to bridge the gap between the demand and supply of electricity. Even while deciding the energy option, the availability of natural resources for future generation and effect of environment for the energy option chosen are to be taken care of. Out of the non conventional sources of electricity, nuclear electricity has greatest potential. Robust and safe energy option has to be harnessed to its potential. We have to bring down the cost of electricity. Even among nuclear reactors, electricity through Fast Breeder Reactors has greater potential. The Prototype Fast Breeder Reactor is a trend setter for moving into an era of electricity generation in the country. The paper brings details of the safety features, accomplishments of the technical challenges and the efforts on hand to reduce the unit energy cost by Nuclear Reactors. The paper also touches upon advantages, environmental impact of Fast Breeder Reactors for this abundant energy resources. Paper will also give a glimpse on technological challenges in design, construction and the preservation. (author)

[en] The Prototype Fast Breeder Reactor (PFBR) being constructed at Kalpakkam is a pool type reactor uses mixed oxide (UO_2+ PuO_2) as fuel and sodium as coolant. Similar to any other nuclear facility, a robust emergency preparedness and response plan approved by AERB is mandatory for commissioning and operation of PFBR. For the preparation of emergency response plan, AERB provides safety requirements and guidance.The latest issue on the subject was released last year by incorporating IAEA guidelines. Emergency Preparedness and Response Manual (EPR) of PFBR is prepared based on the recent guidelines and submitted for approval. Plant specific technical information of PFBR provided in the document based on the revised guidelines are discussed

[en] An investigation of the breeding process is presented. Nuclear physical quantities which can describe the breeding capability of breeder reactors in general terms are discussed. Figure of merit type quantities are reviewed and their ability to describe the breeding capability of fast breeder reactors analyzed. Delays encountered in the use of bred fuel for a system of fast breeder reactors are introduced in the derivation of four general doubling time expressions. The formulas are all based on the accumulating fuel in a growing system of fast breeder reactors. The fuel growth rate, from which the doubling time is obtained, describes the accumulating fuel. Delays incorporated into the expressions include finite burnup in the core and blanket, residence time in the external fuel cycle and holdup in the use of excess bred fuel which fuels new reactors. The first expression is obtained by relating the fuel growth rate to the asymptotic exponential accumulation of fuel for a system of breeder reactors. The second expression is based on single system quantities, e.g., base reactor and its out-of-pile inventory. It is possible because all reactors in the system are defined to be identical. Precalculated coefficients determined from an integrated fuel cycle model are used in the third expression. The fuel cycle is formulated as an eigenvalue problem with the growth rate as eigenvalue and equilibrium plutonium composition as eigenvector. An expression for the doubling time is deduced. The fourth expression is based on ''isotropic breeding worth'' factors. These factors are determined from the adjoint problem to the eigenvalue problem in the third case. The worth factors are identical to the eigenvector of this adjoint problem and the growth rate is again obtained as eigenvalue. The fourth expression is compared with presently applied definitions for a LMFBR in the 1000 MWe range. Dependency investigations are also discussed and analyzed

No abstract available

[en] An Online Nuclear Emergency Response System (ONERS) is developed for the nuclear power plant site at Kalpakkam as part of the Department of Atomic Energy (DAE) initiative. ONERS is a GIS based spatial analysis system designed indigenously to provide decision support in the event of a radioactive leak or accident from any of the nuclear facilities by assessing the dispersion and deposition patterns of the atmospheric releases, integrate with spatial geographical database for impact assessment and guidance for mitigation. The system is designed with open software tools (UMN Map server, MYSQL, PHP, Java scripts) and its main features include assessment of dose, short and long term forecast, counter measure support, impact assessment to minimize potential threat to man and environment during radiological emergencies. The system is implemented in live mode with integration of numerical models and spatial data base for the site region and is presently operational for the Kalpakkam site. (author)

No abstract available

[en] This paper summarizes the studies performed for the Italian PEC fast reactor test facility with regard to flow-induced vibration problems. Reference is made to the reactor-block, the primary and secondary coolant loops and the emergency loops. Studies in progress and future developments foreseen are also mentioned. (author)