the rare earths which have high neutron cross section. The data were analysed to determine the nuclear absorption and the nuclear scattering cross sections.

The thermal (2200-ms/sup -1/)-neutron capture cross section of /sup 107/Ag for the production of metastable /sup 108m/Ag was measured as 0.366 +- 0.065 b, where the uncertainty is nearly all due to the half-life.

in a series of conference designed to bring neutron cross section measurers and users together. The first conference was entitled, "Neu-.

Neutron Capture Cross-section The radiative capture cross-section represents the likelihood of a neutron radiative capture as σγ . As usual, the cross-section can be divided into three regions according to the incident neutron energy. 1/v Region Resonance Region Fast Neutrons Region 1/v Region

The reaction has a high–thermal-neutron cross section (∼3800 b) and exhibits a simple-energy dependence over a wide neutron-energy range, from the thermal energy to ∼30 keV. The

Neutron reaction cross sections. • Total microscopic neutron cross section is expressed as: σ = dN/dt / [(I/A) n A ∆x]. • Defining neutron flux as: φ = I/A 

Neutron cross section standards are important in the measurement and evaluation of all other neutron reaction cross sections. Not many cross sections can be defined as absolute - most are measured relative to the cross section standards. The most recent evaluations were completed in 2005 and a report was published in 2007 (STI/PUB/1291).

Please login to be able to save your searches and receive alerts for new content matching your search criteria. within. Neutron cross section; Journal of 

Specifically, a suitable epithermal neutron flux (ϕEpi) of about 1×109 (n.cm−2.s−1) for BNCT and high quality thermal neutron flux (ϕTh) of above 1×106 (n.cm−2.s−1)for NR are carried

The Atlas of Neutron Capture Cross Sections (NGATLAS) contains cross sections data of neutron induced reactions for targets up to, and including, curium (Z=96). It comprises 739 target isotopes with half-lives above 0.5 day. Cross sections to ground, first and second isomers are listed separately. This gives a total of 972 reaction channels

Table of Simple Integral Neutron Cross-Section Data from JEF-1, ENDF/B-V, ENDL-82,. JENDL-2, KEDAK-4, RCN-3. NEA Data Bank. July 1985. 1. JEF REPORT 3 

Data is presented only for total (i.e., integrated) reaction cross sections (and related fission parameters) as a function of incident-neutron energy. The energy range has been limited to 0.01 eV to 200 MeV in order to exclude crystalline and magnetic effects for slow neutrons and relativistic effects for high energy neutrons.

The neutron cross-section is variable and depends on: Target nucleus(hydrogen, boron, uranium, etc.). Each isotop has its own set of cross-sections. Type of the reaction(capture, fission, etc.). Cross-sections are different for each nuclear reaction. Neutron energy(thermal neutron, resonance neutron, fast neutron).

In a nuclear reactor, nuclides with large neutron capture cross-sections act as poisons in the fuel and diminish performance, or can be 

Neutron Cross Section of the elements Point to the graph to see details, or click for full data on that element. Up to date, curated data provided by Mathematica 's ElementData function from Wolfram Research, Inc. Click here to buy a book, photographic periodic table poster, card deck, or 3D print based on the images you see here!

This group published the first edition of the well-known reference book BNL-325 (Neutron Cross Sections) in 1955. The group's name was changed to the Sigma Center in 1961, then to the National Neutron Cross Section Center in 1967 and finally to the NNDC in 1977, when it was given the additional responsibility for nuclear structure and decay data.

The neutron cross section σ can be defined as the area in cm2 for which the number of nuclei–neutron reactions taking place is equal to the product of the 

Slow Neutron Cross Sections of Gold, Silver, Indium, Nickel, and Nickel Oxide · R. G. Allen, T. E. Stephenson, C. P. Stanford, and Seymour Bernstein · Phys. Rev.

article{osti_4335199, title = {Neutron cross sections. Volume I. Resonance parameters}, author = {Mughabghab, S F and Garber, D I}, abstractNote = {In contrast to earlier editions, which presented in compact form a summary of the complete store of the neutron data files, this edition aims to provide those portions of neutron data considered to be of prime importance and best

During the Manhattan Project, physicists needed to predict the probability of a free neutron striking the nucleus of a fissionable substance, forcing the nucleus to undergo fission. The area within which fission would be expected to occur, is defined to be the "fission cross-section." Fission is not the only potential interaction between

The thermal neutron scattering cross-section of a solid depends on the energy (or wavelength) of the incident neutrons.

A P/sub 3/, 218 neutron group cross-section library in the AMPX master interface format has been generated from ENDF/B-IV data for 65 nuclides of primary interest in criticality safety calculations. The library was generated with the AMPX modular code system. Procedures used to generate the cross sections and the organization of the library are

For most nuclides the scattering lengths and scattering cross sections are independent of the incident neutron wave vector kin the thermal neutron region, 

Neutron cross section of boron (top curve is for 10 B and bottom curve for 11 B) In engineering, the most important neutron absorber is 10 B , used as boron carbide in nuclear reactor control rods or as boric acid as a coolant water additive in pressurized water reactors .

The effects of chemical binding energy on neutron total cross section were investigated by means of elastic and inelastic neutron scattering 

Fast neutron generators driven by isochronous cyclotron U-120M developed at Nuclear Physics Institute were used for neutron cross-section