IN-AIR MEASUREMENTS IN THE VICINITY OF THE TOWER SHIELDING REACTOR II

Technical Report · Mon Apr 01 04:00:00 EST 1963

OSTI ID:4725354

Muckenthaler, F J; Holland, L B; Maerker, R E

During the course of an extensive test program at the Tower Shielding Facility, a large number of measurements were made of the thermal-neutron fluxes and fastneutron and gamma dose rates in air due to radiation emitted by the TSR- II. These free-field'' measurements, so called due to a minimum of structural interferences, were performed for reactor-detector separation distances of 1100 ft, reactor heights of 175 ft, and detector heights of 145 ft. The reactor was encased in two different shields, COOL-I and COOL-II, which were designed to give a fastneutron to gamma physical dose-rate ratio of 1.5 at large distances from the reactor and a thermal-neutron flux leakage 3 that would cause approximates 30% of the gamma dose rates in the field to be due to neutron captures by nitrogen. The significant difference between the two shields was in the hardness of the gamma and fast neutron leakage spectra. A summation of the data obtained and a description of the conditions under which the measurements were made are presented. (auth)

• Research Organization: Oak Ridge National Lab., Tenn.
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-17-019677
• OSTI ID: 4725354
• Report Number(s): ORNL-3288
• Country of Publication: United States
• Language: English

Related Subjects

CAPTURE
DISTRIBUTION
ENERGY
FAST NEUTRONS
GAMMA RADIATION
LOSSES
MEASURED VALUES
NEUTRON FLUX
NEUTRONS
RADIATION DOSES
REACTOR TECHNOLOGY
RESEARCH REACTORS
SCATTERING
SHIELDING
SPECTRA
THERMAL NEUTRONS