Search Results - "Sathe, D.B."

Assaying of SNM using Simultaneous Detection of Fission Neutrons and Gammas by Employing a Novel Phoswich Detector by Sonu, Tyagi, Mohit, Kelkar, A., Sahu, A., Sonawane, M., Sarkar, P.S., Pandey, A., Sathe, D.B., Patra, G.D., Vincent, T., Singh, S.G., Bhatt, R.B.

“…For the precise measurements of special nuclear materials (SNM) including Pu and Am isotopes, we have used phoswich detector combination of two single crystal…”
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Evaluation of micro-homogeneity in plutonium based nuclear reactor fuel pellets by alpha-autoradiography technique by Baghra, Chetan, Sathe, D.B., Sharma, Jitender, Walinjkar, Nilima, Behere, P.G., Afzal, Mohd, Kumar, Arun

“…Alpha-autoradiography is a fast and non-destructive technique which is used at Advanced Fuel Fabrication Facility (India) to evaluate micro-homogeneity of…”
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Fissile worth of MOX fuel: A non destructive study by Vrinda Devi, K.V., Sathe, D.B., Soreng, T.

“…Quality of (U,Pu)O2 mixed oxide (MOX) fuels for fast reactor is judged by its fissile worth; quantified as Pu239 equivalence which is governed by the isotopic…”
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Laser etching of austenitic stainless steels for micro-structural evaluation by Baghra, Chetan, Kumar, Aniruddha, Sathe, D.B., Bhatt, R.B., Behere, P.G., Afzal, Mohd

“…Etching is a key step in metallography to reveal microstructure of polished specimen under an optical microscope. A conventional technique for producing…”
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Direct configuration mode microwave sintering of natural uranium dioxide pellets by Singh, G., Mohod, S., Varma, P.V.S., Purohit, P., Sathe, D.B., Bhatt, R.B.

“…The direct microwave sintering of natural uranium dioxide (UO2) pellets at bulk scale is first time successfully demonstrated. The process of the microwave…”
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Radioactive waste processing using membranes: State of the art technology, challenges and perspectives by Pabby, A.K., Swain, B., Sonar, N.L., Mittal, V.K., Valsala, T.P., Ramsubramanian, S., Sathe, D.B., Bhatt, R.B., Pradhan, S.

“…Among the various separation technologies used to treat radioactive wastes, membrane technologies have been chosen in this article since they have many…”
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On the modification of wire wrapping process for fast Breeder reactor fuel Pins: Replacing hydraulic crimping with resistance spot welding by Kumar, Aniruddha, Kulshrestha, Amit, Aher, Sachin, Kolhatkar, Ashish V, Jayaraj, V.V., Karthik, V., Sathe, D.B., Bhatt, R.B.

“…In this communication we report a modification in the conventional design of wire wrapping process for fast reactor fuel pins and related results. The fuel…”
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Retrieval and processing of radioactive muck settled in the bottom of radioactive liquid waste storage tanks by Prakash, Amrita Dhara, Sonar, N.L., Sah, R.K., De, Vaishali, Thakur, D.A., Mittal, V.K., Valsala, T.P., Sathe, D.B., Bhatt, R.B.

“…•Treatment of chemical muck settled at the bottom of large tanks.•Dissolution of chemical muck in acid mixture.•Borosilicate glass is used for immobilization…”
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Determination of uranium and plutonium in mixed oxide samples by X-ray methods and their comparison with potentiometry by Bootharajan, M., Kumar, G.V.S. Ashok, Sreenivasulu, B., Senthilvadivu, R., Garnayak, P.M., Pandey, A., Kelkar, A., Sathe, D.B., Bhatt, R.B., Rao, C.V.S. Brahmananda, Sundararajan, K., Jayaraman, V., Sivaraman, N.

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Study of plutonium recovery from acidic feed using polyethersulfone encapsulating TBP, DEHPA, and mixture of TBP and DEHPA beads by Guchhait, Satya Ranjan, Patra, Kankan, Yadav, Kartikey K., Singh, D.K., Sengupta, Arijit, Valsala, T. P., Sathe, D.B., Bhatt, R.B.

“…Polyethersulfone (PES) composite beads encapsulating the extractants di-(2-ethylhexyl) phosphoric acid (DEHPA), tributyl phosphoric acid (TBP), and mixture of…”
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Plutonium heterogeneity in MOX fuel: A quantitative analysis by Vrinda Devi, K.V., Ramkumar, Jayshree, Biju, K., Sathe, D.B.

“…(U,Pu)O2 mixed oxide (MOX) fuel has been irradiated in thermal as well as fast reactors in India for Pu utilization. MOX fuels are conventionally fabricated…”
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Thermal expansion and thermal conductivity of (Th,Pu)O2 mixed oxides: A molecular dynamics and experimental study by Somayajulu, P.S., Ghosh, P.S., Arya, A., Devi, K.V. Vrinda, Sathe, D.B., Banerjee, J., Khan, K.B., Dey, G.K., Dutta, B.K.

“…Thermal expansion and thermal conductivity of (Th,Pu)O2 mixed oxides (MOX) have been investigated using molecular dynamics (MD) simulations and experimental…”
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Corrosion and contamination study of nuclear plant steel in HNO3‑Based waste solution with Strontium under nuclear processing environment by Patra, Kankan, Mittal, V.K., Valsala, T.P., Bera, Santanu, Sahu, A.K., Sathe, D.B., Bhatt, R.B.

“…•Deposition of Sr on SS304L from radioactive liquid waste in 3 M HNO3 is studied.•GIXRD showed the presence of SrCrO4 on SS304L surface in 3 M…”
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Characterization and property evaluation of (Th–3.75U)O2+x fuel pellets fabricated by impregnated agglomerate pelletization (IAP) process by Baghra, C., Sathe, D.B., Prakash, A., Mishra, A.K., Afzal, Mohd, Panakkal, J.P., Kamath, H.S.

“…► Characterization of (Th–3.75%U)O2+x pellet fabricated by a new technique i.e., impregnated agglomerate pelletization (IAP). ► Comparison with pellets…”
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A practical method to evaluate radiographic unsharpness by Sathe, D.B., Walinjkar, Nilima, Hinge, A.K., Mukherjee, D., Panakkal, J.P.

“…A simple method for evaluation of total unsharpness of radiographs using wires of different diameters and plaque type penetrameters instead of knife edge…”
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