Browse TRAIL Inventories

An instrument for measuring the logarithm of neutron level and the period of a pile

A study of the slowing down distribution of Sb¹²⁴-Be photo neutrons in graphite, and of the use of indium foils

The total neutron cross sections of Ni⁵⁸ and Ni⁶⁰

Neutron monitoring by means of nuclear track film (NTA) :(supplementary report)

A nuclear plate camera for fast neutron spectroscopy at the bulk shielding facility

An experimental search for the dineutron.

The attenuation of neutrons by air ducts in shields

Neutron slowing down by hydrogen in the consistent P₁ approximation

Neutron scattering

Neutron absorption by fissionable materials in the 5 to 50 Kev energy range

A Monte Carlo calculation of air-scattered neutrons

Conference on Neutron Physics by time-of-flight, held at Gatlinburg, Tennessee, November 1 and 2, 1956.

Effective neutron removal cross sections for carbon and oxygen in continuous mediums

Monte Carlo calculations of fluxes and dose rates resulting from neutrons multiply scattered in air

Theory of resonance absorption of neutrons in a lump

Radiation accidents :dosimetric aspects of neutron and gamma-ray exposures

Proceedings of the neutron thermalization conference, April 28-30, 1958 Gatlinburg, Tennessee

Resonance absorption of neutrons in nuclear reactors

The determination of trace elements in water by neutron activation analysis

Initial post neutron measurements in the ORR

Photoneutrons and the control of a pool-type reactor

Studies of the spherical harmonics method in neutron transport theory.

An evaluation of solid moderating materials

Milne problem with capture

Group-theoretical treatment of time- and energy-dependent multiple scattering, with aplication to the slowing-down of neutrons

Calculations of neutron age in H₂O and other materials

Whirlaway :a three-dimensional, two-group neutron diffusion code for the IBM 7090 computer

New solutions of the Boltzmann equation for monoenergetic neutron transport in spherical geometry

Effects of fast-neutron irradiation and high temperature on beryllium oxide

Equipoise-3 :a two-dimensional, two-group, neutron diffusion code for the IBM-7090 computer

Soluble neutron poisons as a primary criticality control in shielded and contained radiochemical facilities

A literature survey of nonelastic reactions for nucleons and pions incident on complex nuclei at energies between 20 MeV and 33 GeV

In-air measurements in the vicinity of the tower shielding reactor II

The yield of elastically scattered 17 to 21 MeV neutrons from the reaction C¹² (n,n) C¹²

Results of impact tests performed on 55-gal drum-type birdcages

INTRIGUE :an IBM-7090 subroutine package for making linear, logarithmic and semilogarithmic using the CALCOMP Plotter

O5R, a general-purpose Monte Carlo neutron transport code

ISOTOPES :a program for neutron product yields and decay calculations using a control data 1604-A computer

14-Mev neutron reactions

O5S :a Monte Carlo code for calculating pulse height distributions due to monoenergetic neutrons incident on organic scintillators


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