Vividh Hi- Fab

Nuclear Fuel Charging Casks are used for charging of Nuclear Fuel into the reactors. Manufacgtured from IS 2062 Gr.B plates cladded with Stainless Steel 304 L plates and provided with lead shielding.

The equipment is the core of Fast Breeder Reactors. The equipment involved critical machining viz. jig boaring of the core to very stingent tollarances. Fabricated from SS 316 LN material.

SS cladded CS water tank having capacity of 70,000 ltrs. for storage of clean water used for cooling of Cryogenic equipments used by Space Research Centres. Overall dimentions are 15 mtrs. long x 3 mtrs. dia. manufactured from 32 mm thick boiler quality plates cladded with 3 mm thick SS 304 L quality plates weighing approximately 35 MTs.

Application: Roasting of Al.oxide grains
Useful Size: 500 mm dia, 4 mtr length.
Working temperature: 1200°C
Loading: Through bucket elevator & Vibratory feeder.
Heating: By HSD Burner.

The S.S. Vessels are used by the Indian Navy for storage of D2O. The Vessels are manufactured from SS 204L material as per ASME section VIII.

S.S. Glove Boxes are used by Atomic Research Institutes to carryout research of radiation of various radioactive materials. Manufactured from Stainless Steel 304L, IS:2064 Gr. A.

The Head Exchangers of verious designs & sizes are manufactured from Stainless Steel & C.S.Boiler Quality plates & Copper tubes, etc.

spent nuclear fuel shipping flasks are used for shipping spent nuclear fuel from verious atomic power plants to recharging plants. The equipments are manufactured from 45 mm thick is 2062 gr. B. Plates and s. S. 304l plates of verious thickness. The equipment is shielded by lead. The entire equipment is cladded with 6 mm. Thick s. S. 304l plates. The total weight of the equpment is about 65 mts.

The Door consist of two hinged door panels mounted on the door frame and are installed in the Nuclear Reactor’s Hot Cell for containment of radiation within the Hot Cell. The door is approximately 3 mtrs. x 3.5 mtrs. in size and 600 mm. thick weighing approximately 40 M.Tons. made from Carbon Steel IS 2062 plates.

Radionuclide contamination of stainless steel surfaces occurs during submersion in a spent fuel storage pool. Subsequent release or desorption of these contaminants from a nuclear fuel transportation cask surface under varying environmental conditions occasionally results in the phenomenon known as contamination 'weeping'. Experiments have been conducted to determine the applicability of a chemical ion exchange model to characterise the problem of case contamination and release. Surface charge characteristics of Cr2O3 and stainless steel (304) powders have been measured to determine the potential for ion exchange at metal oxide-aqueous interfaces. The solubility of Co and Cs electrolytes at varying pH and the adsorption characteristics of these ions on Cr2O3 and stainless steel powders in aqueous slurries have been studied. Experiments show that Co ions do reversibly adsorb on these powder surfaces and more specifically, that adsorption occurs in the nominal pH range (pH=4-6) of a boric acid moderated spent fuel pool. Desorption has been demonstrated to occur at pH<3. Cs+ ions also have been shown to have an affinity for these surfaces although the reversibility of Cs+ bonding by H+ ion exchange has not been fully demonstrated. These results have significant implications for effective decontamination and coating processes used on nuclear fuel transportation casks.

The Standpipe thimble assemblies are used in Nuclear Power Plants for secondary shutdown systems of the plants. The equipment involved critical machining upto 7 mtrs. long parts. Manufactured from special imported low cobald stainless steel material.

The Sodium Test Vessels used for treatment of Sodium used for coolant in Fast breeder reactors. Manufactured from S.S. 316 LN material. The overall dimentions are 2.8 mtrs. x 15 mtrs. long. The equipments involved critical machining of large flanges & optical alignment of critical components in the Vessel.

The Gammachambers are designed to conform category 1, self-contained, dry source storage type of irradiator as per American National Standard, ANSI N43.7 (1984), Meets the requirments of type B(U) Radioactive package as per AERB Code SC/TR-1, Now. 86 and IAEA Safety Series-6 1985 as `amended in 1990. The Gammachambers have mechanism for rotating/stirring sasmples during irradiation for better uniformity of dose, have low external leakage radiation level of 5 mR/hr, or less 5 cms from the surface with maximum source loading, having provision for introduction of service sleeves for gases, thermocouples, etc. in to the irradiation chamber and have solid state programmable controls provided with battery back up power for operation both in auto and manual modes even during the main power failure. The equipments are shielded for radiation by Lead & Stainless Steel 304 L.

Control Plug & Failed Fuel Locating Module scaled model is manufactured from SS 304L and Carbon Steel IS 2062 material used for research and study of patterns of Fast Breeder Reactors. The model consists of approximately 400 components with very critical tolerances and about 1500 thermocouples and is approximately 2.3 mtrs. in diameter and 8 mtrs. height and weights about 85 M.Tons.

Roof Slab model integral with cylindrical shell (MV) along with 274 nos. of thermo couples and thermal insulations. Small Rotable Plug model for integral top shield model with 274 thermo couples. Manufactured from A 304l , ASTM A 516/A 516 M-03 Gr.65, etc.