[en] The magnetic saturation method can be used to determine absolute delta ferrite content of an austenitic weld metal. This report describes an apparatus based on above method that has been developed at Reactor Research Centre. With this apparatus ferrite measurements can be carried out to an accuracy of +- 1% ferrite. The report also briefly reviews other methods of measuring absolute ferrite content. Results obtained with the apparatus developed at RRC are compared with results from metallographic method and ferritescope and from a similar equipment in another laboratory. (author)

[en] Covariance Matrix based statistical features have been used to detect leak, identify noise source and characterise noise transmission off-line on data from PFR Steam Generator Units. The methods show promise in their ability to detect leak in actual Steam Generator Units from the noise data with very low S/N ratios. Further analysis of data have yielded useful information on the potential of acoustic leak detection system

[en] All penetrations including cable penetrations of the containment building must be leak-tight so that leakage rate for released radioactive material inside the containment building is kept to a minimum. Special leak-proof cables utilising elastic insulating compounds to seal the intrastand and interconductor space have been developed for the cable penetration assemblies for use in the Fast Breeder Test Reactor, Kalpakkam. More than 50 samples of these cables were tested for leak-tightness and the results are presented. Over-all leakage rate for most of the samples of 3 metre length is found to be 0.02%. This rate will be lower by a factor of 10 for an in-field length of 50 meters, because an inverse relationship was observed to exist between cable length and leakage. Leakage is also found to be independent of electrical loading. (M.G.B.)

[en] Noise cross correlation technique is considered as a potential method for calibrating large size sodium flowmeters on test stands and also in-situ during reactor operation and work has been initiated at the Reactor Engineering Laboratory to develop this technique. This paper describes the experiments carried out to calibrate flowmeters of 36 mm pipe size by this technique and the results obtained. (author)

[en] Fast Breeder Reactors have an important role to play in our nuclear power programme. Liquid metal sodium is used as the coolant for removing fission heat generated in fast reactors and a distinctive physical property of sodium is its high electrical conductivity. This enables application of electromagnetic (EM) pumps, working on same principle as electric motors, for pumping liquid sodium. Due to its lower efficiency as compared to centrifugal pumps, use of EM pumps has been restricted to reactor auxiliary circuits and experimental facilities. As part of our efforts to manufacture fast reactor components indigenously, work on the development of two types of EM pumps namely flat linear induction pump (FLIP) and annular linear induction pump (ALIP) has been undertaken. Design procedures based on an equivalent circuit approach have been established and results from testing a 5.6 x 10E-3 Cum/s (20 Cum/h) FLIP in a sodium loop were used to validate the procedure. (author). 7 refs., 6 figs

[en] Modal properties namely, natural frequency and damping factor of the thermal baffles of the 500 MW(e) Prototype Fast Breeder Reactor were measured on a 1/16 scale model. Impulse excitation method was used and experiments were carried out with different levels of water in the annulus between the two baffles. Value of each modal frequency was found to be nearly independent of water level whereas the damping ratio showed a decreasing trend with lower level in the annulus. (author). 2 refs., 5 figs

[en] In this paper the criteria used in the first IAEA coordinated research programme to assess the quality of signal processing techniques for sodium boiling noise detection are highlighted. Signal processing techniques, using new features sensitive to boiling and a new approach for achieving higher reliability of detection, which were developed at Indira Gandhi Centre for Atomic Research are also presented. 10 refs, 3 figs, 2 tabs

[en] Fast Breeder Test Reactor (FBTR) which is expected to become critical shortly is a loop type reactor of 40 MW thermal capacity and has two primary and two secondary centrifugal pumps for heat removal. During the initial periods of reactor operation, the steam generator is bypassed and the secondary sodium pumps are required to operate at flows less than that at best efficiency point. This paper deals with the cavitation problems associated with operation at partial f lows, theoretical estimations and experimental cavitation measurements carried out on FBTR secondary sodium pumps. These investigations revealed that operation of FBTR pumps at this off design condition is free from cavitation damage. Cavitation experiments on a model pump for the development of large sodium pumps for a 500 MWe Prototype Fast Breeder Reactor (PFBR) are described in this paper

[en] Realising the potential of acoustic leak detection technique, an experimental programme was initiated a few years back at Indira Gandhi Centre for Atomic Research (IGCAR) to develop this technique. The first phase of this programme consists of experiments to measure background noise characteristics on the steam generator modules of the 40 MW (thermal) Fast Breeder Test Reactor (FBTR) at Kalpakkam and experiments to establish leak noise characteristics with the help of a leak simulation set up. By subjecting the measured data from these experiments to signal analysis techniques, a criterion for acoustic leak detection for FBTR steam generator will be evolved. Second phase of this programme will be devoted to developing an acoustic leak detection system suitable for installation in the 500 MWe Prototype Fast Breeder Reactor (PFBR). This paper discusses the first phase of the experimental programme, results obtained from measurements carried out on FBTR steam generators and results obtained from leak simulation experiments. Acoustic leak detection system being considered for PFBR is also briefly described. 4 refs, 8 figs, 1 tab

[en] Acoustic detection of sodium boiling is a promising technique to monitor subassembly fault in a last reactor. This paper summarises the programme for developing this detection system and describes the design of a high temperature transducer for boiling detection. It is appreciated that the background noise from primary pumps can interfere with this detection. Noise measurements were therefore carried out during water testing of the primary pump of the Fast Breeder Test Reactor. Some preliminary results of these measurements are presented