Evaluation and Calculation of Activation Cross Sections for ~(158,159)Tb(n,2n), (n,3n), (n,γ) and (n,x) Reactions Below 20 MeV

Introduction ~(159)Tb is a rare-earth element. Its activation cross section is a good indicator for nuclear science and technology applications. However, the evaluated data are very scarce in several nuclear data libraries. The cross section for ~(159)Tb(n,2n)~(158)Tb reaction was one of the Coordinate Research Program of IAEA on activation cross     

Evaluation and Calculation of Activation Cross Sections for ~(169)Tm(n,2n), (n,3n), (n,γ) and (n,x) Reactions Below 20 MeV

Introduction ~(169)Tm is a rare-earth element. Its activation cross sections are a good indicator for nuclear science and technology applications. However, there are no evaluated data in several nuclear data libraries. The activation cross sections for ~(169)Tm(n,2n), (n,3n), (n,γ) and some emission charged particle (n,x) reactions below 20 MeV were evaluated and calculated on the basis of experimental and theoretical data.     

Evaluation of the (n,p) Cross Sections for Natural Ni and Its Isotopes ~(58, 60, 61, 62, 64)Ni

Introduction Nickel is a very important structure material in nuclear engineering. The neutron activation cross section of the (n,p) reaction is very important for fusion reactor from the view point of monitoring neutron field in the context of radiation damage, radiation safety, neutron dosimetry, etc. The cross sections ~(58,60,61,62,64)Ni(n,p)~(58,60,61,62,64)Co were evaluated based on measured data and theoretical calculation from threshold to 20 MeV.     

Activation cross section measurement for ^165Ho（n,γ）^166m Ho and ^151Eu（n,γ）^152g Eu

The cross sections for ^151Eu(n,γ）152gEu reaction in the neutron energy range of 22-1100keV and the cross sections for ^165Ho(n,γ)166m Ho reaction at the neutron energies of 203.676 and 974keV are measured by activation method.The data of the neutron activation cross section at given energy ranges for ^165Ho and ^151Eu are presented for the first time.     

Evaluation of Neutron Monitor Cross Section for ~(197)Au(n,2n)~(196)Au Reaction from Threshold to 80 MeV

The evaluation of intermediate energy nuclear data for the ~(197)Au(n,2n)~196 Au reaction cross section is very important to monitor high energy neutron field, neutron activation, dosimetry and radiation induced material damage etc.. This work was undertaken to provide more precise and complete interme     

Activation Cross Section Measurement of ~(64)Zn(n,γ)~(65)Zn Reaction from 156 to 1150 keV

The neutron capture cross sections are important not only for the studies of nuclear reaction mechanism and astrophysics but also for the nuclear technology application. ~(64)Zn(n,γ)~(65)Zn cross sections are desired for the design of fusion reactor. Up to now, there are a few data for this reaction, but mostly for thermal and fission spectrum neutrons. At the higher neutron energies, no such measurements of ~(64)Zn(n,γ)~(65)Zn activation cross section have been reported.     

Measurement of Activation Cross Sections for ~(159)Tb(n,γ)~(160)Tb and ~(169)Tm(n,γ)~(170)Tm Reactions

Introduction Both ~(159)Tb and ~(169)Tm are rare-earth elements. Their activation cross sections are a good indicator for nuclear science and technology applications. Precise values of the neutron capture cross section of terbium and thulium also are of practical importance in relation to reactor design since they are the fission product poisons.     

Evaluation of Neutron Activation Cross Sections for ~(93)Nb(n,2n)~(92m)Nb and ~(93)Nb(n,n′)~(93m)Nb Reactions from Threshold to 20 MeV

Niobium is a very important structure material in nuclear fusion engineering. The activation cross sections of neutron interaction with ~(93)Nb must be considered for the evaluation of radiation safety, radiation induced material damage. Meanwhile, knowledge of the neutron(n,2n) and (n,n') reactions have been used for the neutron dosimetry. The dosimetry reaction of ~(93)Nb(n,n')~(93m)Nb is characterized by the low threshold energy less than 0.1     

THE MEASUREMENT AND ANALYSIS OF ~(98)Mo(n,γ) ~(99)Mo REACTION CROSS SECTION

INTRODUCTION Radioactivity in fusion reactors is induced by D-T neutrons and dependon the materials chosen for reactor components.The need for activationcross-sections leading to the production of long-lived(half-life longer thanfive years)radionuclides has become obvious in the recent years because of theworldwide concerns for the production of high level nuclear waste from fusionreactors.These important activation cross section,which still need to be meas-     

Measurement of Cross Section for ~(92)Mo(n,p)~(92m)Nb Reaction and Deduction of Low Energy Neutron

Introduction Molybdenum is an important component of structural material for fission and future fusion reactors. It consists of seven isotopes. Therefore, fast neutrons can lead to many nuclear reactions. One of them is ~(92)Mo(n,p)~(92m)Nb reaction. Several authors published their data for this reaction, while most of the cross section determinations were     

Evaluation of Activation Cross Sections for (n,2n) and (n,γ) Reactions on ~(63, 65, Nat)Cu

Copper is a very important structure material in nuclear fusion engineering. The neutron activation cross section are very useful in fusion research and other applications such as radiation safety, environmental, material damage and neutron dosimetry. More efforts are required to identify and resolve the differences and discrepancies in the existing activation cross sections from different laboratories. The natural copper consists of two stable isotopes, i.e. ~(63)Cu, ~(65)Cu. The reaction Q-Values and abundances are listed in Table 1.     

COMMUNICATION OF NUCLEAR DATA PROGRESS No.16(1996)

This is the 16th issue of Communication of Nuclear Data Progress (CNDP), in which the achievements in nuclear data field for the last year in P. R. China and a paper from India are carried. It includes the measurements of neutron activation cross section for ~(193)Ir (n, 2n) ~(192m2)Ir reaction at 14.7 MeV     

Cross Section Measurement for Reaction ~(193)Ir(n,2n)~(192m2)Ir at 14.7 MeV

The cross sections induced by neutron on long-lived radionuclides of importance in fusion reactor technology are measured by activation method for ~(193)Ir(n,2n)~(192m2)Ir reaction at 14.7 MeV. The neutron fluences are determined by the cross section of ~(93)Nb(n,2n)~(92m)Nb. The neutron energies in these measurements are determined by cross section ratios for ~(90)Zr(n,2n)~(89)zr and ~(93)Nb(n,2n)~(92m)Nb reactions.     

Evaluation of Activation Cross Sections for (n,α) and (n,n'α) Reactions on ~(63, 65, Nat)Cu

Introduction Copper is a very important structure material in nuclear fusion engineering. The neutron activation cross section are very useful in fusion research and other applications such as radiation safety, environmental, material damage and neutron dosimetry. More efforts are required to identify and resolve the differences and discrepancies in the existing activation cross sections from different laboratories. The natural copper consists of two stable isotopes, i.e. ~(63)Cu, ~(65)Cu. Their abundaces and threshold energies are given in Table 1.     

Cross Section Measurement of ~(64)Zn(n,p)~(64)Cu Reaction from 4 to 7 MeV

Introduction In the areas of activation and neutron scattering cross sections, there are still deficiencies in the nuclear database. Activation cross sections were found to be unsatisfactory in 83 of the 183 reactions reviewed. The excitation curve for ~(64)Zn(n,p)~(64)Cu reaction has been measured from threshold to 10 MeV by different authors. All of these measured cross sections are not in very good agreement with each other. To clarify the discrepancy it is necessary to measure the cross sections for ~(64)Zn(n,p)~(64)Cu reaction once again.     

Measurement of Double Differential Cross Sections for ~(39)K(n,α)~(36)Cl Reaction

Introduction ~(39)K(n,α)~(36)Cl reaction data are important in nuclear engineering, nuclear medicine, astrophysics as well as in the study of nuclear mechanism. As we know, experimental data for ~(39)K(n,α)~(36)Cl reaction are scanty and there is no double differential datum. The double differential cross section data of ~(39)K(n,α)~(36)Cl reaction were measured at 4.41±0.26, 5.46±0.21 and 6.52±0.16 MeV using a gridded ionization chamber (GIC).     

Activation Cross Section Measurement for the Eu(n,γ) Reactions

The cross sections for ~(151)Eu(n,γ)~(152m)Eu, ~(151)Eu(n,γ)(152g)Eu and ~(153)Eu(n,γ)~(154)Eu reactions have been measured relatively to that of ~(197)Au for neutron energy from 22 to 1100 keV, using the activation technique. Neutrons were generated via the ~7Li(p,n)~7Be and T(p,n)~3He reaction with a 4.5 MV Van de Graaff accelerator at Peking University. The activities after irradiation were measured with two calibrated high resolution HPGe detectors. The accuracy of the measurement is 6～7%. The experiment results were compared with existing data.     

Study on Method of Measuring ~(128)I(n,γ)Reaction Cross Section by Accelerator Mass Spectrometry

<正>The thermal neutron cross section of ~(128)I(n,γ)~(129)I is an important parameter in the research of nuclear physics.For the national application data,stellar evolution model,reactor design,waste disposal and other research has important applications.At present,this reaction cross section has no experimental data in the world.     

Evaluation of Activation Cross Sections for (n,2n) Reactions on ~(58, 60, 61, 62, 64, Nat)Ni

Introduction Nickel is a very important structure material in nuclear fusion engineering. The neutron activation cross section are very useful in fusion research and other applications such as radiation safety, environmental, material damage and neutron dosimetry. More efforts are required to identify and resolve the discrepancies in the existing activation cross sections from different laboratories. The natural nickel consists of five stable isotopes. Their abundaces and threshold energies are shown in Table 1.     

Evaluation of Activation Cross Sections for (n,p) and (n,n′p) Reactions on ~(63,65,Nat)Cu

Introduction Copper is a very important structure material in nuclear fusion engineering. The neutron activation cross section are very useful in fusion research and other applications such as radiation safety, environmental, material damage and neutron dosimetry. More efforts are required to identify and resolve the differences and