Journal of nuclear engineering & technology (vol4, issue1) by STM Journals Publication

Journal of Nuclear Engineering & Technology (JoNET) ISSN: 2321-6514

Jan - April 2014

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STM JOURNALS

I take the privilege to present the hard copy compilation for the [Volume 4 Issue (1)] of Journal of Nuclear Engineering & Technology. The intension of JoNET is to create an atmosphere that stimulates creativeness, research and growth in the area of Nuclear Engineering & Technology. The development and growth of the mankind is the consequence of brilliant Research done by eminent Scientists and Engineers in every field. JoNET provides an outlet for Research findings and reviews in areas of Nuclear Engineering & Technology found to be relevant for National and International recent developments & research initiative. The aim and scope of the Journal is to provide an academic medium and an important reference for the advancement and dissemination of Research results that support high level learning, teaching and research in the domain of Nuclear Engineering & Technology. Finally, I express my sincere gratitude and thanks to our Editorial/ Reviewer board and Authors for their continued support and invaluable contributions and suggestions in the form of authoring writeups/ reviewing and providing constructive comments for the advancement of the journals. With regards to their due continuous support and co-operation, we have been able to publish quality Research/Reviews findings for our customers base. I hope you will enjoy reading this issue and we welcome your feedback on any aspect of the Journal.

Dr. Archana Mehrotra Director STM Journals

Journal of Nuclear Engineering & Technology

Contents

1. Kinetics of Ion-Isotopic Exchange Reactions using Nuclear Grade Resins Purolite NRW-4000 and Purolite NRW-6000 P.U. Singare 1 2. Performance Evaluation Studies of Purolite NRW-5010 and Indion AGR Anion Exchange Resins by Radioactive Tracer Technique P.U. Singare

3. Assessment of Two Phase Turbulent Mixing Models for Subchannel Analysis Relevant to BWR M.P. Sharma, A.K. Nayak

4. A Survey of Genetic Algorithm Applications in Nuclear Fuel Management M.L. Jayalal, S.A.V. Satya Murty, M. Sai Baba

Journal of Nuclear Engineering & Technology ISSN: 2321-6514 Volume 4, Issue 1 www.stmjournals.com

Kinetics of Ion-Isotopic Exchange Reactions using Nuclear Grade Resins Purolite NRW-4000 and Purolite NRW-6000 P.U. Singare* Department of Chemistry, Bhavan’s College, Munshi Nagar, Andheri (West), Mumbai, India

Abstract The paper deals with an application of nondestructive radio isotopic tracer technique in performance evaluation of two nuclear grade anion exchange resins Purolite NRW-4000 and Purolite NRW-6000. The technique was used to study the kinetics of bromide and iodide ion-isotopic exchange reactions taking place between the external ionic solution and the resin surface for which 131I and 82Br were used as tracer isotopes. It was observe that at a constant temperature of 30°C when the concentration of iodide ions in solution increases from 0.001 to 0.004 mol/L, the specific reaction rate values for iodide ionisotopic exchange increases from 0.325 to 0.368 min-1 for Purolite NRW-6000, while in case of Purolite NRW-4000, under identical experimental conditions, the specific reaction rate values increases from 0.268 to 0.315 min-1. However, when the concentration of iodide ions in solution is kept constant at 0.001 mol/L and temperature is raised from 30 to 45°C, in case of Purolite NRW-6000 the specific reaction rate values for iodide ion-isotopic exchange decreases from 0.325 to 0.310 min-1, while in case of Purolite NRW-4000, under identical experimental conditions, the specific reaction rate values for iodide ion-isotopic exchange decreases from 0.268 to 0.251 min-1. Also it was observed that at a constant temperature of 30°C, as the concentration of labeled iodide ion solution increases from 0.001 to 0.004 mol/L, the percentage of iodide ions exchanged increases from 76.40 to 83.32% using Purolite NRW-6000 resins. While under the same experimental conditions using Purolite NRW-4000 resins the percentage of iodide ions exchanged increases from 67.32 to 74.88 %. The identical trend was observed for the two resins during bromide ion-isotopic exchange reaction. The overall results indicate that as compared to Purolite NRW-4000 resins, Purolite NRW-6000 resins shows superior performance under identical experimental conditions.

Keywords: Nuclear grade resins, tracer isotopes, nondestructive technique, ion-isotopic exchange, reaction kinetics, purolite NRW-4000, purolite NRW-6000, 131 82 I, Br

Journal of Nuclear Engineering & Technology ISSN: 2321-6514 Volume 4, Issue 1 www.stmjournals.com

Performance Evaluation Studies of Purolite NRW-5010 and Indion AGR Anion Exchange Resins by Radioactive Tracer Technique P.U. Singare* Department of Chemistry, Bhavan’s College, Munshi Nagar, Andheri (West), Mumbai, India

Abstract The characterization of organic base anion exchange resins Purolite NRW-5010 and Indion AGR was made by application of short lived radio tracer isotopes 131I and 82Br. The characterization of the two resins was based on their performance during iodide and bromide ion-isotopic reaction taking place between the resin surface and the external labeled ionic solution. The exchange reactions were carried out by using the ionic solution in the concentration range of 0.001 to 0.004 mol/L and temperature varying from 30 to 45.0°C. It was observed that during iodide ion-isotopic exchange reaction taking place at 40°C using 1.000 g of ion exchange resins and 0.003 mol/L labeled iodide ion solution, the values of specific reaction rate (min-1), amount of ion exchanged (mmol), initial rate of ion exchange (mmol/min) and log Kd were calculated as 0.251, 0.485, 0.122 and 11.4, respectively for Purolite NRW-5010 resin, which was higher than the respective values of 0.098, 0.323, 0.032 and 5.4 as obtained for Indion AGR resins. Also at a constant temperature of 40°C, as the concentration of labeled iodide ion solution increases from 0.001 to 0.004 mol/L, the percentage of iodide ions exchanged increases from 60.00 to 66.20% for Purolite NRW-5010 resins and from 41.20 to 43.80% for Indion AGR resins. The similar trend was observed for the two resins during bromide ion-isotopic exchange reaction. From the overall results it appears that as compared to Indion AGR resins, under identical experimental conditions Purolite NRW-5010 resins shows superior performance.

Keywords: Anion exchange, ion exchange resins, Purolite NRW-5010, Indion AGR, radio isotopes, 131I, 82Br, characterization, ion-isotopic exchange reactions

Page 13

Journal of Nuclear Engineering & Technology ISSN: 2321-6514 Volume 4, Issue 1 www.stmjournals.com

Assessment of Two Phase Turbulent Mixing Models for Subchannel Analysis Relevant to BWR M.P. Sharma1*, A.K. Nayak2 1

Homi Bhabha National Institute, Anushaktinagar, Mumbai, India 2 Bhabha Atomic Research Centre, Trombay, Mumbai, India

Abstract Determination of turbulent mixing rate of two phase flow between neighboring subchannels is an important aspect of subchannel analysis in reactor rod bundles. Various models have been developed for two phase turbulent mixing rate between subchannels. These models show that turbulent mixing rate is strongly dependent on flow regimes; their validity was examined against specific or limited experiments. It is vital to evaluate these models by comparing the predicted two phase turbulent mixing rate with available experimental data conducted for various subchannel geometries and operating conditions. This paper describes evaluation of different models for two phase turbulent mixing rate for both gas and liquid phase against large range of experimental data which are obtained from various subchannel geometries. The results indicate that there is large discrepancy between the predicted and experimental data for turbulent mixing rate.

Keywords: Subchannel analysis, two phase turbulent mixing model, turbulent mixing rate

Journal of Nuclear Engineering & Technology ISSN: 2321-6514 Volume 4, Issue 1 www.stmjournals.com

A Survey of Genetic Algorithm Applications in Nuclear Fuel Management M.L. Jayalal*, S.A.V. Satya Murty, M. Sai Baba Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, India Abstract The prime aim of nuclear fuel management is to achieve higher fuel utilization without compromising safety during reactor operation. Nuclear fuel management optimization is a classical nuclear engineering problem, which has been studied for more than four decades and several techniques have been used for its solution. Genetic algorithm is one among the major global optimization techniques, used in the field of nuclear fuel management. Aim of this paper is to survey genetic algorithm related developments happened during the last few decades in nuclear fuel management optimization. The objectives of this survey are: (i) to summarize how genetic algorithm is applied to the field of nuclear fuel management (ii) to compare different genetic algorithm techniques and operators used in solving the nuclear fuel management optimization problems (iii) to bring out current trends and future directions in this field. The survey will help the researchers in the field to get an overview about genetic algorithm techniques available for nuclear fuel management optimization and how to use them.

Keywords: Genetic algorithm, nuclear fuel management, multi objective genetic algorithm, constrained optimization, parallel genetic algorithm, crossover, mutation