Jan - April 2014

STM JOURNALSScientific Technical Medical

ISSN: 2321-6514

(JoNET)

Journal of Nuclear

Engineering & Technology

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Journal of Nuclear Engineering & Technology

Journal of Nuclear Engineering & Technology

(ISSN: 2321–6514)

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Industrial Tribology Machine Dynamics & Maintenance

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Indian Institute of Technology Delhi, India

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Alternative Energy Technology Laboratory,

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Chandigarh, India.

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Dr. Ketan Pravinchandra DetrojaAssistant Professor, Department of

Electrical Engineering, Indian Institute of Technology Hyderabad,

Yeddumailaram, Andhra Pradesh, India.

Nikolai ChecheninSkobeltsyn Institute of Nuclear Physics of

Moscow State University, Russian Federation, Russia.

Dr. Howard Lewis Hall University of Tennessee, United States.

Lin ShaoDept of Nuclear Engineering Texas

A&M University, United States.

Amritanshu Shukla Rajiv Gandhi Institute of Petroleum

Technology Raebareli, Ratapur Chowk Raebareli, U.P. India.

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.

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their continued support and invaluable contributions and suggestions in the form of authoring write-

ups/ 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

Director's Desk

STM JOURNALS

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 13

3. Assessment of Two Phase Turbulent Mixing Models for Subchannel Analysis Relevant to BWRM.P. Sharma, A.K. Nayak 25

4. A Survey of Genetic Algorithm Applications in Nuclear Fuel ManagementM.L. Jayalal, S.A.V. Satya Murty, M. Sai Baba 45

ContentsJournal of Nuclear Engineering & Technology

JoNET (2014)© STM Journals 2014. All Rights Reserved

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 131

I and 82

Br 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 ion-

isotopic 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

I, 82

Br

JoNET (2014) 13-24 © STM Journals 2014. All Rights Reserved Page 13

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 131

I and 82

Br. 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, 131

I, 82

Br, characterization, ion-isotopic exchange reactions

JoNET (2014)© STM Journals 2014. All Rights Reserved

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

1Homi Bhabha National Institute, Anushaktinagar, Mumbai, India

2Bhabha 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

JoNET (2014)© STM Journals 2014. All Rights Reserved

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