[en] An artificial neural network model is applied to the task of reactivity monitoring in a nuclear reactor. The network is trained using a maximum likelihood method. The adaptability of the network to slow variations in the system parameters and its ability to learn in a noisy environment are demonstrated. (author). 15 refs., 5 figs

[en] Additional Spent Subassembly Storage Facility (ASSSF) is proposed to be built within PFBR complex to accommodate additional storage for spent fuel subassemblies, fresh fuel subassemblies and long term storage for absorber, shielding and reflector subassemblies. The present study is for estimating k_eff of the spent fuel storage bay in ASSSF. It is a water pool storage of dimension 4400 cm x 910 cm as shown. 1005 fuel subassemblies can be stored in the storage bay. The fuel subassemblies are stored in triangular pitch with pitch distance 32 cm. Storage bay is filled with de-mineralized water up to a height of 4.5 m above the subassemblies.

[en] The nuclear data, i.e., the numerical information about every nuclide - especially those representing the probabilities of various nuclear interactions and of radioactivity - of interest in a nuclear fission reactor are among the most essential inputs to be known a priori, to the best possible accuracy, for the design of nuclear reactor. The nuclides of interest cover not just (1) the fuel nuclides, the containers, the coolant, the moderator (if any), etc., that are initially inserted, but also (2) the actinides, the fission products, etc. that would be produced from the moment the reactor goes into operation and (3) the decay products that are produced even while the reactor is shutdown. The nuclide-list is known to cover a few hundreds. The neutron-nuclear interaction cross-section data, required for a few tens of reactions, very sensitively depend on the nuclide species and the neutron energy. Hence the data requirement significantly varies between thermal and fast reactors. The present talk is intended to touch upon the kinds and forms of nuclear data needed in the design and analysis of fast reactors. The recent variants available in the databases and some inter-comparison results will also be presented. (author)

[en] FBR 1 & 2 is a pool type homogeneous fast reactor of thermal power 1500 MWth and electrical power 600 MWe. In a pool type fast reactor, intermediate heat exchanger is immersed in primary sodium pool. Secondary sodium flowing through tube side of IHX gets activated which then goes to steam generator building and results in radiation doses at steam generator building. Due to large neutron flux and harder neutron spectrum, limited choice of materials in high temperature and restricted space available for shielding makes it a difficult task to design in-vessel shield. Especially in the case of FBR 1 & 2, leakage in the top axial direction has increased due to removal of top axial blanket to minimize sodium void. In this paper, calculation and design of top shield has been carried out to achieve minimum primary sodium gamma dose rate in top shield working platform

[en] Additional Spent Subassembly Storage Facility (ASSSF) proposed to be built within PFBR complex has an additional storage area to accommodate fresh fuel subassemblies. This study is for estimating shield requirement for the fresh fuel subassembly storage bay in ASSSF. It is a dry storage vault. Totally 232 fuel subassemblies can be stored. Fuel subassemblies are stored in a triangular pitch with pitch distance 32 cm

[en] This paper examines the role of the k/N systems in improving the reliability of the radiation monitoring systems with β factor Common Cause Factor (CCF) model

[en] Prototype Fast Breeder Reactor (PFBR) is a 500 MWe, sodium cooled, mixed oxide fuelled, pool type fast reactor being constructed at Kalpakkam, India. PFBR has two independent and diverse Decay Heat Removal (DHR) systems viz., Operating Grade Decay Heat Removal System (OGDHRS) and Safety Grade Decay Heat Removal System (SGDHRS). The present work reports the reliability analysis of the dampers of the SGDHR system. The relay logic, actuators, valves, power supply and mechanical part of dampers are modeled for both the electrical and pneumatic dampers of SGDHRS. This work includes the results of two cases viz., i) Failure probability of each of the dampers to assess the performance of individual electrical and pneumatic damper in a loop, and ii) Failure probability of SGDHR dampers in a single loop. The second case includes common cause failures of motors, class II system, valves and relays. Uncertainty analysis and sensitivity studies have also been carried out for both electric and pneumatic dampers

[en] FBR 1 & 2 is a pool type homogeneous fast breeder reactor of thermal power 1500 MWth and electrical power 600 MWe. In a pool type fast reactor, intermediate heat exchanger (IHX) is immersed in primary sodium pool. Under neutron irradiation, the secondary sodium flowing through IHX gets activated

[en] Use of Monte Carlo simulation is becoming increasingly important in the domain of detector development for radiation detection application recently. In this paper, 3D continuous energy code MCNP was used to generate theoretical response function of a Nested Neutron Spectrometer (NNS)

[en] This work aims to obtain self-shielding factors (G) for several activation foils, including copper, tungsten, magnesium, molybdenum, hafnium, and indium in neutron spectrum energy measurements in the various beam tubes of KAMINI reactor. Knowing the self-shielding factors allows for precise nuclear reaction rates to be obtained without the effects of neutron flux depression inside activation foils. (author)