Optimized Control Rod of the Research Reactor BR2

Total Page:16

File Type:pdf, Size:1020Kb

Optimized Control Rod of the Research Reactor BR2 BNEN Belgian Nuclear Higher Education Network BNEN Vrije Universiteit Brussel • Universiteit Gent • Katholieke Universiteit Leuven • Université de Liège • Université Catholique de Louvain • Studiecentrum voor Kernenergie – Centre d’Étude de l’Énergie Nucléaire●Université Libre de Bruxelles CONFIDENTIAL Optimized Control Rod of the Research Reactor BR2 BNEN/2006-2007 Xingmin Liu Promotor: Prof. Dr. Ir. Jean-Marie NOTERDAEME, UGent Academic year 2006-2007 Thesis submitted in partial fulfilment of the requirements for the degree of Master of Science in Nuclear Engineering Belgian Nuclear Higher Education Network, c/o SCK•CEN, Boeretang 200, BE-2400 Mol, Belgium BNEN Belgian Nuclear Higher Education Network BNEN Vrije Universiteit Brussel • Universiteit Gent • Katholieke Universiteit Leuven • Université de Liège • Université Catholique de Louvain • Studiecentrum voor Kernenergie – Centre d’Étude de l’Énergie Nucléaire●Université Libre de Bruxelles All property right and copy right are reserved. Any communication or reproduction of this document and any communication or use of its contents without explicit authorisation is pro- hibited. Any infringement to this rule is illegal and entitles to claim damages from the infringer, without prejudice to any other right in case of granting a patent of registration in the field or intellectual property. 1 © BNEN, Belgian Nuclear Education Network ii Master of Science in Nuclear Engineering Thesis Summary Page Name of the student: Xingmin Liu Title: Optimized nuclear control of the research reactor BR2 Abstract: At the present time the BR2 reactor uses Control Rods with cadmium as neutron absorbing part. The lower section of the Control Rod is a beryllium assembly cooled by light water. A capsule containing about 190 grams of cobalt granules is inserted between the lower part of the cadmium section and the upper part of the beryllium follower. Due to the burn up of the lower end of the cadmium section during the reactor operation, the presently used rods for reactivity control of the BR2 reactor have to be replaced by new ones. Considered are various types Control Rods with full active part of the following materials: cadmium (Cd), hafnium (Hf), europium oxide (Eu2O3) and gadolinium oxide (Gd2O3). Options for decrease of the burn up of the control rod material in the hot spot, such as use of stainless steel in the lower active part of the Control Rod are discussed. Comparison with the characteristics of the presently used Control Rods types is performed. The changing of the characteristics of different types Control Rods and the perturbation effects on the reactor neutronics during the BR2 fuel cycle are investigated. The burn up of the Control Rod absorbing material, total and differential control rods worth, macroscopic and effective microscopic absorption cross sections, fuel and reactivity evolution are evaluated during ~ 30 operating cycles, which is equivalent to ~ 1000 EFPD of reactor operation. The calculations are performed for the full scale 3-D heterogeneous geometry model of BR2 using MCNP&ORIGEN-S combined method. A criterion for choice of the new control rod types is presented. The main procedures for control of the BR2 reactor are revisited and modified to satisfy the new irradiation conditions. Promotor: Prof. Dr. Ir. Jean-Marie Noterdaeme Approval for submission by promotor: Mentors: Ir. Edgar Koonen Dr. Silva Kalcheva Assessors: Prof. Dr. Ir. Pierre-Etienne Labeau Prof. Dr. Ir.Greet Janssens-Maenhout Academic Year 2006-2007 Belgian Nuclear Higher Education Network, c/o SCK•CEN, Boeretang 200, BE-2400 Mol, Belgium Acknowledgement I would like to express my gratitude to all those who gave me the possibility to complete this thesis. I want to thank the department of BR2 of SCKyCEN for providing me such a good thesis and a very comfortable office to do this thesis. I would like to express my sincere gratitude to my promoter Prof. Dr. Ir. Jean-Marie Noterdaeme who kept an eye on the progress of my work. I am very grateful to my mentor Edgar Koonen for his important support, help and for all his kindness. It is difficult to overstate my gratitude to another mentor Dr. Silva Kalcheva. With her patience, she taught me the using of code, gave me a lot of good advices at the beginning and helped me solve all the questions throughout the thesis. Without her help, I could not finish my thesis in time. Finally, I would like to give special thanks to my wife. During the study, she took on all family affairs alone, I owe her too much. iv Summary At the present, the BR2 reactor uses Control Rods with cadmium as neutron absorbing part. The lower section of the Control Rod is a beryllium assembly cooled by light water. A capsule containing about 190 grams of cobalt granules is inserted between the lower part of the cadmium section and the upper part of the beryllium follower. Due to the burn up of the lower end of the cadmium section during the reactor operation, the presently used rods for reactivity control of the BR2 reactor have to be replaced by new ones. A modification design for the control rod will be developed. Chapter 1 mainly introduces the importance of control reactivity for a reactor, and then gives a general idea of how to choose a kind of control rod material with good characteristics; finally, according to historical experiences of BR2 operation, shows the importance and the aim of this thesis. The choice of control rod materials is related to the characteristics of BR2, therefore, in Chapter 2 the main description of BR2 reactor will be introduced, which can help us to know how to choose an appropriate control rod type among those candidate materials for BR2. The central topic in the Chapter 3 is the choice of control rod material. Firstly, the general condition of research reactors in the world will be introduced and the basic parameters including control rod material will be listed. Secondly, Chapter 3 describes the detailed characteristics from macroscopic to microscopic of several important absorbing materials such as cadmium (Cd), hafnium (Hf), europium oxide (Eu2O3), gadolinium oxide(Gd2O3) and stellite. The characteristics of these candidate materials will determine the behavior of the rod in the core during irradiation. The calculation methodologies will be given in Chapter 4. The methods of completing the thesis are chiefly numerical methods (application of appropriate computational tools) complemented with analytical considerations (based on reactor kinetics theory) and experimental methods (measurement of the reactor period). The behavior of the control rod is time-dependent, so the reactor kinetics theory is the main principle, which lies in the basis for determination of the reactor period. Therefore, the first part Chapter 4.1 gives some theoretical aspects of the processes of reactor kinetics for the case of a slab reactor combined with the real parameters of BR2. The aim of this chapter is: starting from the one-speed diffusion equation and through the equations of the reactor kinetics to deduce step by step the formula for the reactor period. Several numerical solutions of the kinetics equations are given in Appendices. The reactor period is the main parameter to be measured and to be used in the experimental technique for determination of control rod worth. Therefore, in the second part Chapter 4.2 the experimental method will be also introduced as a kind of validation and certification method to theory analysis and calculation. The basic computational tools used in this thesis for determination of the control rod characteristics are MCNP, SCALE4.4a and MCNP&ORIGEN-S method. The functions of these codes and how to use them to solve the task of the thesis will be discussed in Chapter 4.3. v The first several chapters mostly introduce some knowledge related to the optimal design. With the theoretical support of these chapters, Chapter 5 mainly discusses what should be calculated, that means, we must know what are the factors affecting the behavior of the control rod in the BR2 and what is the criterion of the optimal design. On the basis of those, the calculation will be started. At first, choosing several ideal CR types with different absorbing material, and then modeling using the MCNP Monte Carlo code complemented with time-dependent evaluations by SCALE4.4a, finally, the process of calculation will be given. The content of Chapter 6 is analysis of calculation results which is the most important section in the thesis. The analysis method is the comparison. We can proceed from three main aspects: comparison of CR material characteristics during irradiation, comparison of the reactor neutronics characteristics of BR2 with different type of CR, and comparison of neutron flux distribution with different type of CR. For the first aspect, the comparison includes five terms: macroscopic absorption cross sections, activity, nuclear heating in the lower active part of the control rods, total control rods worth’s and differential control rod worth; for the second aspect, we do the comparison for the keff and reactivity variations during the operating cycle; for the third aspect, we compare the axial distribution of the neutron flux for both the various types of CR at same position and the same type of CR at the different position of the control rod. The final conclusion is given in Chapter 7. The conclusion of each section in the last chapter will be summarized, according to which, a most optimal CR type is chosen as the new control rod type and the detailed reasons are presented. Although the material has been chosen, the ideal dimension of CR has not yet been decided, therefore, the final step is to compare the different dimensions so as to get a most optimal design. vi Contents CHAPTER 1 INTRODUCTION........................................................................................................................ 1 CHAPTER 2 THE OVERVIEW OF BR2.........................................................................................................
Recommended publications
  • Measurement and Analysis of the Resolved Resonance Cross Sections of the Natural Hafnium Isotopes
    CORE Metadata, citation and similar papers at core.ac.uk Provided by University of Birmingham Research Archive, E-theses Repository MEASUREMENT AND ANALYSIS OF THE RESOLVED RESONANCE CROSS SECTIONS OF THE NATURAL HAFNIUM ISOTOPES by TIMOTHY CHRISTOPHER WARE A thesis submitted to The University of Birmingham for the degree of DOCTOR OF PHILOSOPHY School of Physics and Astronomy College of Engineering and Physical Sciences The University of Birmingham June 2010 University of Birmingham Research Archive e-theses repository This unpublished thesis/dissertation is copyright of the author and/or third parties. The intellectual property rights of the author or third parties in respect of this work are as defined by The Copyright Designs and Patents Act 1988 or as modified by any successor legislation. Any use made of information contained in this thesis/dissertation must be in accordance with that legislation and must be properly acknowledged. Further distribution or reproduction in any format is prohibited without the permission of the copyright holder. ABSTRACT Hafnium is a ductile metallic element with a large neutron absorption cross section. It can be used in reactor control rods to regulate the fission process. The NEA High Priority Request List for nuclear data presents a need for improved characterisation of the hafnium cross section in the resolved resonance region. This thesis presents new resonance cross section parameters for the six natural hafnium isotopes. Cross section measurements, supported by the NUDAME and EUFRAT projects, were performed at the IRMM Geel GELINA time-of-flight facility. Capture experiments were conducted on the 12 m, 28 m and 58 m flight paths using C6D6 detectors and transmission experiments were performed at flight paths of 26 m and 49 m using a 6Li glass detector.
    [Show full text]
  • First Search for $\Alpha $ Decays of Naturally Occurring Hf Nuclides With
    First search for α decays of naturally occurring Hf nuclides with emission of γ quanta F.A. Danevicha,1, M. Hultb, D.V. Kasperovycha, G.P. Kovtunc,d, K.V. Kovtune, G. Lutterb, G. Marissensb, O.G. Polischuka, S.P. Stetsenkoc, V.I. Tretyaka aInstitute for Nuclear Research, 03028 Kyiv, Ukraine bEuropean Commission, Joint Research Centre, Retieseweg 111, 2440 Geel, Belgium cNational Scientific Center Kharkiv Institute of Physics and Technology, 61108 Kharkiv, Ukraine dKarazin Kharkiv National University, 61022 Kharkiv, Ukraine ePublic Enterprise “Scientific and Technological Center Beryllium”, 61108 Kharkiv, Ukraine Abstract The first ever search for α decays to the first excited state in Yb was performed for six isotopes of hafnium (174, 176, 177, 178, 179, 180) using a high purity Hf-sample of natural isotopic abundance with a mass of 179.8 g. For 179Hf, also α decay to the ground state of 175Yb was searched for thanks to the β-instability of the daughter nuclide 175Yb. The measurements were conducted using an ultra low-background HPGe-detector system located 225 m underground. After 75 d of data taking no decays were detected but lower 15 18 bounds for the half-lives of the decays were derived on the level of lim T1/2 ∼ 10 −10 a. The decay with the shortest half-life based on theoretical calculation is the decay of 174Hf to the first 2+ 84.3 keV excited level of 170Yb. The experimental lower bound was found 15 to be T1/2 ≥ 3.3 × 10 a. Keywords: Alpha decay; 174Hf, 176Hf, 177Hf, 178Hf, 179Hf, 180Hf, Low-background HPGe γ spec- trometry arXiv:1911.02597v1 [nucl-ex] 6 Nov 2019 1 INTRODUCTION Alpha decay is one of the most important topics of nuclear physics both from the theoretical and experimental points of view.
    [Show full text]
  • 4.62 Samarium
    IUPAC 4.62 samarium Stable Relative Mole isotope atomic mass fraction 144 Sm 143.912 01 0.0308 147 † Sm 146.914 90 0.1500 148 Sm † 147.914 83 0.1125 149 Sm 148.917 19 0.1382 150 Sm 149.917 28 0.0737 152 Sm 151.919 74 0.2674 154 Sm 153.922 22 0.2274 † Radioactive isotope having a relatively long half-life and a characteristic terrestrial isotopic composition that contributes significantly and reproducibly to the determination of the standard atomic weight of the element in normal materials . The half-lives of 147 Sm and 148 Sm are 1.06 × 10 11 years and 7 × 10 15 years, respectively. 4.62.1 Samarium isotopes in Earth/planetary science One possible origin for the Moon is from debris ejected by an indirect giant impact of Earth by an astronomical body the size of Mars when the Earth was forming [433]. The kinetic energy liberated is thought to have melted a large part of the Moon forming a lunar magma ocean. P.O. 13757, Research Triangle Park, NC (919) 485-8700 IUPAC Samarium isotope measurement results [434], along with measurements of isotopes of hafnium, tungsten, and neodymium[435], suggest that lunar magma formed about 70 × 10 6 years after the Solar System formed and had crystallized by about 215 × 10 6 years after formation. 147 Sm is used to study the formation of potassium, rare earth elements , and phosphorus-rich rocks [436]. 4.62.2 Samarium isotopes in geochronology 147 Sm is used for determining formation ages of igneous and metamorphic rocks via analysis of the minerals which compose them, such as those shown in Figure 4.62.1 [437-439].
    [Show full text]
  • Concurrent Reduction and Distillation; an Improved Technique for the Recovery and Chemical Refinement of the Isotopes of Cadmium and Zinc*
    If I CONCURRENT REDUCTION AND DISTILLATION; AN IMPROVED TECHNIQUE FOR THE RECOVERY AND CHEMICAL REFINEMENT OF THE ISOTOPES OF CADMIUM AND ZINC* H. H. Cardill L. E. McBride LOHF-821046—2 E. W. McDaniel DE83 001931 Operations Division Oak Ridge National Laboratory Oak Ridge, Tennessee 3 7830 .DISCLAIMER • s prepared es an accouni oi WOTk sconsQ'ed by an agency of itie United Slates Cover r "iiit?3 Stilt 65 Gov(?fnft»gn ^ ri(jt ^nv aQcncy Tllf GO* ^or rlny O^ tt^^ir ^rnployut^. TigV MASTER lostifl. ion, apod'aiuj pioiJut;. <y vned nghtv Reference hcein xc any v>t^-'T*t. ^ Dv ^.r^de narno, tf^Oernafk^ mir'ij'iJClureT. or otrierw «d <Jo*^ •nenaalion. or liivONng bv 'Vhe United _^_ . vs and opinions of authors enp'«i«] herein do noi IOM t' irip UnitK* Stales Govefnrneni c a^v agency For presentation at the 11th World Conference of the International Nuclear Target Development Society, October 6-8, 1982, Seattle, Washington. By acceptance of this article, the publisher or recipient acknowledge* the U.S. Govarnment's right to retain a nonaxclusiva, royalty-frtta license in and to any copyright covering tha article. NOTICE P0T09_0£-Jfns,J^SPQRT_JfgE_Il,LESIBLE. I has been reproauce.1 from the best available aopy to pensit the broadest possible avail- ability* *Research sponsored by the Office of Basic Energy Science, U.S. Department of Energy under contract W-7405-eng-26 with the Union Carbide Co rpcration,, DISTRIBUTION OF THIS DOCUMEHT 18 UNLIMITED ' CONCURRENT REDUCTION AND DISTILLATION - AY. IMPROVED TECHNIQUE FOR THE RECOVERY AND CHEMICAL REFINEMENT OF THE ISOTOPES OF CADMIUM AND ZINC H.
    [Show full text]
  • KULAGE-DISSERTATION-2013.Pdf
    ENCRYPTED NANOPARTICLES FOR SECURITY, COUNTER-INDUSTRIAL ESPIONAGE, AND COUNTERFEITING A Dissertation by ZACHARY ANDREW KULAGE Submitted to the Office of Graduate and Professional Studies of Texas A&M University in partial fulfillment of the requirements for the degree of DOCTOR OF PHILOSOPHY Chair of Committee, William S. Charlton Committee Members, Sean M. McDeavitt John W. Poston, Sr. Charles M. Folden III Head of Department, Yassin A. Hassan December 2013 Major Subject: Nuclear Engineering Copyright 2013 Zachary Andrew Kulage ABSTRACT Acts of terrorism and the use of explosives raise concerns about what can be done to prevent such acts. From stopping such a threat to preventing the illicit counterfeiting and smuggling of sensitive and proprietary goods, identification tag- gant technology can be applied to identify and interdict materials of a dubious na- ture. This cost effective approach to tag and track materials will find application in both the government and private sectors, particularly in the prevention of corporate espionage. A taggant system was created based on the modification of the natural isotopic vector of cadmium and tellurium to create artificial, unique, and robust identification capabilities. A proof of concept trial was undertaken to ascertain the effectiveness, reliability, and integrity of a system. Stable isotopes were mixed in various combi- nations to alter the isotopic vector and then neutron activation analysis techniques were used to evaluate the quality of the taggants. Two different neutron activation analysis facilities of differing capabilities were employed to test the limitations of the method in detection of trace amounts of taggant material. Testing of the taggant system found that solid phase taggants were capable of producing around 14,000 unique taggants for under $250 each while liquid phase taggants were capable of producing around 2,000 unique taggants for under $50 each.
    [Show full text]
  • Neutron Capture Cross Sections of Cadmium Isotopes
    Neutron Capture Cross Sections of Cadmium Isotopes By Allison Gicking A thesis submitted to Oregon State University In partial fulfillment of the requirements for the degree of Bachelor of Science Presented June 8, 2011 Commencement June 17, 2012 Abstract The neutron capture cross sections of 106Cd, 108Cd, 110Cd, 112Cd, 114Cd and 116Cd were determined in the present project. Four different OSU TRIGA reactor facilities were used to produce redundancy in the results and to measure the thermal cross section and resonance integral separately. When the present values were compared with previously measured values, the differences were mostly due to the kind of detector used or whether or not the samples were natural cadmium. Some of the isotopes did not have any previously measured values, and in that case, new information about the cross sections of those cadmium isotopes has been provided. Table of Contents I. Introduction………………………………………………………………….…….…1 II. Theory………………………………………………………………………...…...…3 1. Neutron Capture…………………………………………………….….……3 2. Resonance Integral vs. Effective Thermal Cross Section…………...………5 3. Derivation of the Activity Equations…………………………………....…..8 III. Methods………………………………………………………….................…...…...12 1. Irradiation of the Samples………………………………………….….....…12 2. Sample Preparation and Parameters………………..………...………..……16 3. Efficiency Calibration of Detectors…………………………..………....…..18 4. Data Analysis…………………………………...…….………………...…..19 5. Absorption by 113Cd……………………………………...……...….………20 IV. Results………………………………………………….……………..……….…….22
    [Show full text]
  • Arxiv:1305.1738V1 [Nucl-Ex] 8 May 2013 Ae Pcrsoystpa SLECR.High-Energy ISOLDE-CERN
    Spins, Electromagnetic Moments, and Isomers of 107-129Cd D. T. Yordanov,1,2, ∗ D. L. Balabanski,3 J. Biero´n,4 M. L. Bissell,5 K. Blaum,1 I. Budinˇcevi´c,5 S. Fritzsche,6 N. Fr¨ommgen,7 G. Georgiev,8 Ch. Geppert,6, 7 M. Hammen,7 M. Kowalska,2 K. Kreim,1 A. Krieger,7 R. Neugart,7 W. N¨ortersh¨auser,6, 7 J. Papuga,5 and S. Schmidt6 1Max-Planck-Institut f¨ur Kernphysik, Saupfercheckweg 1, D-69117 Heidelberg, Germany 2CERN European Organization for Nuclear Research, Physics Department, CH-1211 Geneva 23, Switzerland 3INRNE, Bulgarian Academy of Science, BG-1784 Sofia, Bulgaria 4Instytut Fizyki imienia Mariana Smoluchowskiego, Uniwersytet Jagiello´nski, Reymonta 4, 30-059 Krak´ow, Poland 5Instituut voor Kern- en Stralingsfysica, KU Leuven, Celestijnenlaan 200D, B-3001 Leuven, Belgium 6GSI Helmholtzzentrum f¨ur Schwerionenforschung GmbH, D-64291 Darmstadt, Germany 7Institut f¨ur Kernchemie, Johannes Gutenberg-Universit¨at Mainz, D-55128 Mainz, Germany 8CSNSM-IN2P3-CNRS, Universit´ede Paris Sud, F-91405 Orsay, France (Dated: October 7, 2018) The neutron-rich isotopes of cadmium up to the N = 82 shell closure have been investigated by high-resolution laser spectroscopy. Deep-UV excitation at 214.5 nm and radioactive-beam bunching provided the required experimental sensitivity. Long-lived isomers are observed in 127Cd and 129Cd for the first time. One essential feature of the spherical shell model is unambiguously confirmed by − a linear increase of the 11/2 quadrupole moments. Remarkably, this mechanism is found to act well beyond the h11/2 shell. PACS numbers: 21.10.Ky, 21.60.Cs, 32.10.Fn, 31.15.aj When first proposed the nuclear shell model was protons impinging on a tungsten rod produced low- to largely justified on the basis of magnetic-dipole proper- medium-energy neutrons inducing fission in a uranium ties of nuclei [1].
    [Show full text]
  • Atomic Weights of the Elements 2013 (IUPAC Technical Report)
    Pure Appl. Chem. 2016; 88(3): 265–291 IUPAC Technical Report Juris Meija*, Tyler B. Coplen, Michael Berglund, Willi A. Brand, Paul De Bièvre, Manfred Gröning, Norman E. Holden, Johanna Irrgeher, Robert D. Loss, Thomas Walczyk and Thomas Prohaska Atomic weights of the elements 2013 (IUPAC Technical Report) DOI 10.1515/pac-2015-0305 Received March 26, 2015; accepted December 8, 2015 Abstract: The biennial review of atomic-weight determinations and other cognate data has resulted in changes for the standard atomic weights of 19 elements. The standard atomic weights of four elements have been revised based on recent determinations of isotopic abundances in natural terrestrial materials: cadmium to 112.414(4) from 112.411(8), molybdenum to 95.95(1) from 95.96(2), selenium to 78.971(8) from 78.96(3), and thorium to 232.0377(4) from 232.038 06(2). The Commission on Isotopic Abundances and Atomic Weights (ciaaw.org) also revised the standard atomic weights of fifteen elements based on the 2012 Atomic Mass Evaluation: aluminium (aluminum) to 26.981 5385(7) from 26.981 5386(8), arsenic to 74.921 595(6) from 74.921 60(2), beryllium to 9.012 1831(5) from 9.012 182(3), caesium (cesium) to 132.905 451 96(6) from 132.905 4519(2), cobalt to 58.933 194(4) from 58.933 195(5), fluorine to 18.998 403 163(6) from 18.998 4032(5), gold to 196.966 569(5) from 196.966 569(4), holmium to 164.930 33(2) from 164.930 32(2), manganese to 54.938 044(3) from 54.938 045(5), niobium to 92.906 37(2) from 92.906 38(2), phosphorus to 30.973 761 998(5) from 30.973 762(2), praseodymium to 140.907 66(2) from 140.907 65(2), Article note: Sponsoring body: IUPAC Inorganic Chemistry Division Committee: see more details on page 289.
    [Show full text]
  • Isotopic Composition of Some Metals in the Sun
    SNSTITUTE OF THEORETICAL ASTROPHYSICS BLINDERN - OSLO REPORT .No. 35 ISOTOPIC COMPOSITION OF SOME METALS IN THE SUN by ØIVIND HAUGE y UNIVERSITETSFORLAqET • OSLO 1972 Universitetsfc lagets trykningssentral, Oslo INSTITUTE OF THEORETICAL ASTROPHYSICS BLINDERN - OSLO REPORT No. 35 ISOTOPIC COMPOSITION OF SOME METALS IN THE SUN by ØIVIND HAUGE UNIVERSITETSFORLAGET • OSLO 1972 Universitetsforlagets tryknlngssentral, Oslo CONTENTS Abstract 1 1. Introduction 2 2. Fine structure in spectral lines from atoms 5 1. Isotope shift 5 2. Hyperfine structure 6 3. Applications to atomic lines in photospheric spectrum .... 8 1. Elements with one odd isotope , 9 2. Elements with two odd isotopes 9 3. Elements with one odd and several even isotopes 11 k. Elements with several odd and even isotopes 11 h. Studies of elements in the Sun with two odd isotopes 1. Isotopes of rubidium 12 A. Observations lk B. Calculations 16 C. The Rb I line at 78OO Å 1. The continuum level 16 2. Line profiles and turbulent velocities 18 3. The asymmetry of the Si I line 19 h. Isotope investigations 21 P. The Rb I line at 79^7 A 28 E. The isotope ratio of rubidium 31 F. The abundance of rubidium 3k 2. Isotopes of antimony 35 A. Spectroscopic data 35 B. The Sb I lines at 3267 and 3722 A 37 3* Isotopes of europium 1*0 A. Observations and methods of analysis ^1 B. Spectroscopic data 1*1 C. Spectral line investigations 1. Investigations of four Eu II lines **3 2. The Eu II lines at Ul29 and U205 k ^6 D. The isotope ratio of europium 50 E.
    [Show full text]
  • A Modified Nuclear Model for Binding Energy of Nuclei And
    A MODIFIED NUCLEAR MODEL FOR BINDING ENERGY OF NUCLEI AND THE ISLAND OF STABILITY BY KENNETH KIPCHUMBA SIRMA A THESIS SUBMITTED IN PARTIAL FULFILMENT OF THE REQUIREMENTS FOR THE AWARD OF THE DEGREE OF DOCTOR OF PHILOSOPHY IN PHYSICS, UNIVERSITY OF ELDORET, KENYA. MAY, 2021 ii DECLARATION Declaration by the Candidate I declare that this is my original and personal work and has not been presented for a degree in any other university. This thesis is not to be reproduced without the prior written permission of the author and/or University of Eldoret. Kenneth Kipchumba Sirma ______________________________ _______________________ SC/PHD/002/15 Date Approval by Supervisors This thesis has been submitted for examination with our approval as University Supervisors. ______________________________ _______________________ Prof. Kapil M. Khanna Date Department of Physics University of Eldoret, Kenya. ______________________________ _______________________ Dr. Samuel L. Chelimo Date Physics Department University of Eldoret, Kenya. iii DEDICATION To my beloved mum Grace for her unconditional love, advice and support. To our children Gael and Abby you are blessings. My wife Jacinta, for her love and care. iv ABSTRACT A new nuclear model of quantifying binding energy of nuclei is proposed. The nucleus is assumed to be composed of two regions; the inner core region and surface region. The inner core is assumed to be composed of Z proton-neutron pairs (Z=N) and the surface region is composed of the unpaired neutrons for a nucleus in which N>Z. The interaction between the core and neutrons in the surface region is assumed to be such that it leads to an average potential Vo in which each neutron in the surface region can move.
    [Show full text]
  • On-Line Separation of Short-Lived Tungsten Isotopes from Tantalum; Hafnium and Lutetium by Adsorption on Ion Exchangers from Aqueous Ammonia Solution
    Jointly I,ublished by Elsevier Scie.ce S. A~. Lausanne and J.Radioanal.Nucl.Chem.,Letters Akad?miai Kiod6, Bltdapest 214 (I) I-7 (I 996) ON-LINE SEPARATION OF SHORT-LIVED TUNGSTEN ISOTOPES FROM TANTALUM; HAFNIUM AND LUTETIUM BY ADSORPTION ON ION EXCHANGERS FROM AQUEOUS AMMONIA SOLUTION 1 1 1 1 D. Schumann , R. Dressler , St. Taut , H. Nitsche , Z. Szeglowski2, B. Kubica2~ L.I. Guseva 3, 4 G.S. Tikhomirova3, A. Yakushev~, O. Constantinescu , V.P. Domanov 4, M. Constantinescu 4, Dinh Thi Lien 4, Yu. Ts. Oganessian 4, V.B. Brudanin 4, I. Zvara 4, H. Bruchertseifer 5 I Institute of Analytical Chemistry, University of Technology Dresden, 01062 Dresden, Germany 2H. Niewodniczanski Institut of Nuclear Physics, Krakow, Poland ~Institute of Geochemistry and Analytical Chemistry, Moscow, Russia 4joint Institute of Nuclear Research, Dubna, Russia 5paul-Scherrer-Institute, Villigen, Switzerland Received 17 June 1996 Accepted I July 1996 The title goal was achieved using a DOWEX 50Wx8 cation exchange column saturated with La(OH) 3 and ammonia solution as eluent.>Hf, Ta and Lu were adsorbed on this column, where- as W remained in the solution. This chemical system may be used for fast on-line separa- tions of element 106. INTRODUCT ION Subgroup VI elements form oxo-anions in alkaline solu- tion I , whereas subgroup IV and V elements and lanthanides hydroiyze under these conditions. This might be of inter- 0236 -5 731/76/.[/S ~ J 2,0 Cops I"ight ~'9~6 Ak~ch~nlirli KicaM, Blldapr All t il.,ht$ rest'tied SCHUMANN et al.: ON-LINE SEPARATION OF TUNGSTEN ISOTOPES est for fast on-line separation of element 106 from heavy actinides and element 104 produced simultaneously in heavy ion reactions.
    [Show full text]
  • Radiochemical Analysis: Activation Analysis, Instrumentation, Radiation Techniques, and Radioisotope Techniques July 1964 to June 1965
    NAT'L INST OF STAND & TECH R.I.C. mil in mi mi ii 111 inn A111DS 3S3fibM National Bureau 01 oiwiuarua Refer Library,.ibr N.UL^ldg ffg'l4^6 taken ^ecltniccil ^lote 276 RADIOCHEMICAL ANALYSIS: ACTIVATION ANALYSIS, INSTRUMENTATION, RADIATION TECHNIQUES, AND RADIOISOTOPE TECHNIQUES JULY 1964 TO JUNE 1965 U. S. DEPARTMENT OF COMMERCE NATIONAL BUREAU OF STANDARDS THE NATIONAL BUREAU OF STANDARDS The National Bureau of Standards is a principal focal point in the Federal Government for assur- ing maximum application of the physical and engineering sciences to the advancement of technology in industry and commerce. Its responsibilities include development and maintenance of the national standards of measurement, and the provisions of means for making measurements consistent with those standards; determination of physical constants and properties of materials; development of methods for testing materials, mechanisms, and structures, and making such tests as may be neces- sary, particularly for government agencies; cooperation in the establishment of standard practices for incorporation in codes and specifications; advisory service to government agencies on scientific and technical problems; invention and development of devices to serve special needs of the Govern- ment; assistance to industry, business, and consumers in the development and acceptance of com- mercial standards and simplified trade practice recommendations; administration of programs in cooperation with United States business groups and standards organizations for the development of international standards of practice; and maintenance of a clearinghouse for the collection and dissemination of scientific, technical, and engineering information. The scope of the Bureau's activities is suggested in the following listing of its three Institutes and their organizational units.
    [Show full text]