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AbstractAbstract
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Journal Article
Journal
Mechanical Engineering; v. 94(2); p. 28-31
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Bloch, M.; Borgado, A.
Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil)1986
Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil)1986
AbstractAbstract
[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.)
Original Title
Projeto de uma secao de teste para analise de escoamento em feixe de sete barras com arranjo hexagonal e arame espacador helicoidal
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Source
Apr 1986; 45 p; Available from the Nuclear Information Center of Comissao Nacional de Energia Nuclear, RJ (BR)
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Report
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Prabhat Kumar, E-mail: pkumar@igcar.gov.in
Proceedings of the national seminar cum workshop on water and energy: sustainability and security for future needs - abstracts and souvenir2012
Proceedings of the national seminar cum workshop on water and energy: sustainability and security for future needs - abstracts and souvenir2012
AbstractAbstract
[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)
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Source
Department of Chemical Engineering, Dwarkadas J. Sanghvi College of Engineering, Mumbai (India); 60 p; Sep 2012; p. 11-12; WAVE 2012: national seminar cum workshop on water and energy - sustainability and security for future needs; Mumbai (India); 27-28 Sep 2012
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Book
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AbstractAbstract
No abstract available
Original Title
Le reacteur surregenerateur rapide refroidi au gaz
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Source
International conference on fast reactors; Aix-en-Provence, France; 02 Sep 1971
Record Type
Journal Article
Literature Type
Conference
Journal
Bull. Inform. Sci. Tech. (Paris); (no.162); p. 15-18
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Reference NumberReference Number
INIS VolumeINIS Volume
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Sudhasini, T.; Shanthi, G.; Sarangapani, R.; Ananth, Allu, E-mail: sudhasini_bhavini@igcar.gov.in
Proceedings of the international conference on radiological safety in workplace, nuclear facilities and environment: book of abstracts2016
Proceedings of the international conference on radiological safety in workplace, nuclear facilities and environment: book of abstracts2016
AbstractAbstract
[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
Primary Subject
Source
Indian Association for Radiation Protection, Mumbai (India); 287 p; 2016; p. 194; IARPIC-2016: 32. international conference on radiological safety in workplace, nuclear facilities and environment; Kalpakkam (India); 22-25 Feb 2016; 1 ref.
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Book
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Borg, R.C.
Purdue Univ., Lafayette, Ind. (USA)1976
Purdue Univ., Lafayette, Ind. (USA)1976
AbstractAbstract
[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
Primary Subject
Source
1976; 158 p; University Microfilms Order No. 77-1686; Thesis (Ph. D.).
Record Type
Report
Literature Type
Thesis/Dissertation
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Dalle Donne, E.; Wirtz, K.
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Neutronenphysik und Reaktortechnik1972
Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Neutronenphysik und Reaktortechnik1972
AbstractAbstract
No abstract available
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Source
Oct 1972; 23 p; EUR--4845-E; 2 figs.; 9 tabs.; 79 refs. With abstract in English and German.
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Report
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Raja Shekhar, S.S.; Bhatawadekar, Shantanu; Krishna Murthy, Y.V.N.; Srinivas, C.V.; Venkatesan, E-mail: ssraj@isro.gov.in, E-mail: sarraju_raj@rediffmail.com
Proceedings of the nineteenth national symposium on radiation physics: research and application of radiation physics - perspective and prospective2012
Proceedings of the nineteenth national symposium on radiation physics: research and application of radiation physics - perspective and prospective2012
AbstractAbstract
[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)
Primary Subject
Source
Mohanakrishnan, P. (ed.) (Reactor Physics Division, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)); Gopalakrishnan, V. (ed.) (Radiological Safety Division, Electronics, Instrumentation and Radiological Safety Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)); Kannan, V. (ed.); Jose, M.T.; Chandrasekaran, S. (Radiological Safety Division, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)) (eds.); Indian Society for Radiation Physics, Mumbai (India); Indira Gandhi Centre for Atomic Research, Kalpakkam (India); Indian Nuclear Society, Kalpakkam Branch, Kalpakkam (India); 636 p; 2012; p. 597-600; NSRP-19: 19. national symposium on radiation physics; Mamallapuram (India); 12-14 Dec 2012; 7 refs., 6 figs.
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Book
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AbstractAbstract
No abstract available
Original Title
Le attivita di ricerca e sviluppo del programma reattori veloci italiano
Primary Subject
Source
Comitato Nazionale per l'Energia Nucleare, Rome (Italy); Serie Simposi; p. 315-365; 1974; CNEN; Rome; Nuclear energy days; Milan, Italy; 14 Dec 1972
Record Type
Book
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Conference
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INIS VolumeINIS Volume
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Lakshminarayana, B.; Phani Babu, C.; Dubey, A.K.; Surender, A.; Deshpande, K.V.K.; Maity, P.K., E-mail: bharathabln@rediffmail.com
Proceedings of the third international conference on characterization and quality control of nuclear fuels2009
Proceedings of the third international conference on characterization and quality control of nuclear fuels2009
AbstractAbstract
[en] India's three stage Nuclear Power Program has entered its second stage on commercial scale with the commencement of construction of 500 MWe Prototype Fast Breeder Reactor (PFBR) at Kalpakkam. Nuclear Fuel Complex (NFC), Hyderabad is playing a crucial role in the manufacture of all the critical sub-assemblies and control elements for this reactor. The challenging task of process development and production of the various critical tubing for these sub assemblies for PFBR has been taken up by Stainless Steel Tubes Plant (SSTP), NFC with indigenous development of the equipment and technology
Primary Subject
Source
Nuclear Fuel Complex, Hyderabad (India); International Atomic Energy Agency, Vienna (International Atomic Energy Agency (IAEA)); Board of Research in Nuclear Sciences, Mumbai (India); 186 p; 2009; 3 p; CQCNF-2009: 3. international conference on characterization and quality control of nuclear fuels; Hyderabad (India); 18-20 Feb 2009
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Book
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Conference
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