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R. Dierckx, W. Haye (1983)
Neutron Signal Multiplet Analysis for the Mass Determination of Spontaneous Fission IsotopesNuclear Science and Engineering, 85
Ming-Shih. Lu, T. Teichmann (1993)
Error Propagation for Gamma Spectroscopy and Neutron Coincidence Counting for Plutonium-Bearing MaterialsNuclear Technology, 102
P. Roy, C. Ganguly (1984)
Plutonium metallurgy in IndiaBulletin of Materials Science, 6
P. Hart, D. Olander (1978)
Plutonia particle behavior during the sintering of mixed oxide fuelsJournal of Nuclear Materials, 78
N. Dytlewski, M. Krick, N. Ensslin (1993)
Measurement variances in thermal neutron coincidence countingNuclear Instruments & Methods in Physics Research Section A-accelerators Spectrometers Detectors and Associated Equipment, 327
A. Dodaro, F. Frazzoli, R. Remetti (1998)
Passive Neutron Assay of Plutonium Materials: Monte Carlo Procedures to Simulate Generation of Neutron Pulse Trains and the Application of the Neutron Coincidence Counting MethodNuclear Science and Engineering, 130
L. Alamos, J. Swansen, P. Collinsworth, Neutron Counters, M. Krick (1980)
Shift-register coincidence electronics system for thermal neutron countersNuclear Instruments and Methods, 176
S. Abousahl, P. Belle, H. Ottmar (2005)
Combined calorimetry/neutron coincidence counting/gamma spectrometry (CANEGA) measurements for plutonium mass and isotopic assayNuclear Instruments & Methods in Physics Research Section A-accelerators Spectrometers Detectors and Associated Equipment, 543
S. Muralidhar, R. Tripathi, B. Tomar, G. Gubbi, S. Dange, S. Majumdar, S. Manohar (2003)
Nondestructive assay of the fissile content in FBTR fuel pinsNuclear Instruments & Methods in Physics Research Section A-accelerators Spectrometers Detectors and Associated Equipment, 511
R. Lerch, R. Norman (1984)
Nuclear Fuel Conversion and Fabrication Chemistry, 36
J. Drummond, R. Grant (1966)
Potentiometric determination of plutonium by argentic oxidation, ferrous reduction and dichromate titration.Talanta, 13 3
R. Ceo, K. Thompson (2000)
Some NDA Techniques Applied to International Safeguards ProjectsJournal of Radioanalytical and Nuclear Chemistry, 243
W. Hage, D. Cifarelli (1985)
Correlation Analysis with Neutron Count Distributions in Randomly or Signal Triggered Time Intervals for Assay of Special Fissile MaterialsNuclear Science and Engineering, 89
Mixed oxide (MOX) fuel is an alternative to conventional enriched uranium oxide fuel in thermal reactors. Indian interest in plutonium recycle in thermal reactors is primarily due to the need to develop alternative indigenous fuel for two boiling water reactors (BWR) at Tarapur, which are designed to use imported light enriched uranium fuel. A few MOX assemblies have been fabricated and loaded into the reactors. Neutron well coincidence counting (NWCC) system has been successfully employed to check the enrichments of PuO 2 in MOX blends. NWCC has also been successfully applied in developing dry recycling process of clean rejected oxide (CRO) and dirty rejected oxide (DRO).
Journal of Radioanalytical and Nuclear Chemistry – Springer Journals
Published: Aug 1, 2008
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