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A fast detector for the scanning of thermal neutron flux profiles in the isotope channels of the FR2
Schuelken, H.
Kernforschungszentrum Karlsruhe (F.R. Germany). Abt. Reaktorbetrieb und Technik1970
Kernforschungszentrum Karlsruhe (F.R. Germany). Abt. Reaktorbetrieb und Technik1970
AbstractAbstract
No abstract available
Original Title
Ein schneller Detektor zur Aufnahme thermischer Neutronenflussdichteprofile in den Isotopenkanaelen des FR2
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Sep 1970; 14 p; 4 tabs.; 9 figs.
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AbstractAbstract
No abstract available
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Comitato Nazionale per l'Energia Nucleare, Rome (Italy); Serie Simposi; p. 241-253; 1971; CNEN; Rome; Nuclear symposium on technical and economic aspects of heavy water production; Turin, Italy; 30 Sep 1970
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Hatcher, S.R.
The AECL symposium on engineering development in nuclear power held at the Chalk River Nuclear Laboratories on May 27 and 28, 19711971
The AECL symposium on engineering development in nuclear power held at the Chalk River Nuclear Laboratories on May 27 and 28, 19711971
AbstractAbstract
No abstract available
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Source
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs; p. 41-45; Nov 1971; AECL symposium on engineering development in nuclear power; Chalk River, Ontario, Canada; 27 May 1971
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AbstractAbstract
No abstract available
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Electrical News and Engineering; v. 81(3); p. 28-29, 31, 40
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AbstractAbstract
[en] An investment cost study for a 1100 MW(e) pressurized heavy water reactor (PHWR) central station power plant is described. Cost differentials relative to a PWR plant are presented
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Jun 1977; 388 p; Available from NTIS., PC A17/MF A01
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Bhatt, T.U.; Tiwari, A.P., E-mail: tarangb@barc.gov.in, E-mail: aptiwari@barc.gov.in
Proceedings of the third national symposium on advances in control and instrumentation2014
Proceedings of the third national symposium on advances in control and instrumentation2014
AbstractAbstract
[en] This paper presents the identification procedure for finding out mathematical model of Liquid Zone Control System (LZCS). The modelling goal is to produce a mathematical description in state space form that is suitable for control-oriented model analysis and controller design. Measurement data from the LZCS test set up have been used for the identification using standard least squares error technique. It is shown that the model is fairly well identifiable. (author)
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Tiwari, A.P.; Chauhan, Vikas; Wakankar, Amol; Karnani, Urvashi; Saxena, Nikhil; Haridasan, Remya; Mishra, Elina (Reactor Control Division, Bhabha Atomic Research Centre, Mumbai (India)) (eds.); Bhabha Atomic Research Centre, Mumbai (India); 769 p; 2014; p. 398-404; SACI-2014: 3. national symposium on advances in control and instrumentation; Mumbai (India); 24-26 Nov 2014; 6 refs., 6 figs.
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AbstractAbstract
[en] In PHWR, Liquid Zone Control System has been used to control zone power in reactor. This system is designed to maintain average power by controling water level in zone compartment which is divided to 14 parts. we need effective model and simulation to examine control performance and operation characteristics, but because it is so difficult to find all of the hydro-thermodynamics of the system and various nonlinear elements was included to the system potentially, analytical modeling is limited. Thus, In this paper we deal with nonlinear modeling with Hammerstein model and simulate the system and demonstrated the results
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Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2003; [12 p.]; 2003 autumn meeting of the KNS; Yongpyong (Korea, Republic of); 30-31 Oct 2003; Available from KNS, Taejon (KR); 5 refs, 13 figs
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Miscellaneous
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AbstractAbstract
[en] In the Indian pressurised heavy water reactors (PHWRs), refuelling is done on-power. A flow assisted refuelling mode is currently being studied, as an alternative to the existing machine assisted refuelling scheme. This mode entails, a special component called flow assisted ram extension (FARE) during refuelling operations. The objective of this paper is to discuss a mathematical model which has been developed to determine the hydraulic characteristics of FARE. (author). 12 refs., 11 figs
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Srinivasa Murthy, S.; Jaluria, Y. (eds.); Indian Society for Heat and Mass Transfer, Madras (India); 975 p; ISBN 0-07-462307-9; 
; 1996; p. 699-704; Tata McGraw-Hill Publishing Company Limited; New Delhi (India); 2. ISHMT-ASME heat and mass transfer conference; Surathkal (India); 28-30 Dec 1995; 13. national heat and mass transfer conference; Surathkal (India); 28-30 Dec 1995
; 1996; p. 699-704; Tata McGraw-Hill Publishing Company Limited; New Delhi (India); 2. ISHMT-ASME heat and mass transfer conference; Surathkal (India); 28-30 Dec 1995; 13. national heat and mass transfer conference; Surathkal (India); 28-30 Dec 1995
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[en] An Argentinian-German joint venture has recently completed detailed design work on PHWR 300 - a pressurized heavy water reactor in the 275MWe-380MWe size range. The design builds on proven technology and is particularly suited to technology transfer. (author)
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Metcalfe, R.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1972
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1972
AbstractAbstract
No abstract available
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Source
Mar 1972; 29 p; 2 refs.
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