FFTF shield and gamma-ray measurements
An extensive measurements program was carried out prior to routine operation of the Fast Flux Test Facility (FFTF) to establish (1) the attenuation characteristics of the reactor shield, (2) the nuclear environment in the core, and (3) to assure that the facility could be operated safely from the standpoint of radiological considerations. Reactor shield neutron fluxes were measured primarily using radioactivant detectors irradiated in special test vehicles placed at assessible locations. Preliminary evaluation of the data indicated shield performance consistent with design calculations. Gamma ray measurements employed a variety of ionization chambers and calorimeters as well as thermoluminescent dosimeters, selfpowered gamma ray detectors, and thermal expansion difference temperature monitors. The gamma ray experimental results are consistent and also in relatively good agreement with analytical predictions. Plant shield survey employed standard radiation survey instruments.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 5583851
- Report Number(s):
- HEDL-SA-2755-FP; CONF-830538-19; ON: DE84001478
- Resource Relation:
- Conference: 6. international conference on radiation shielding, Tokyo, Japan, 16 May 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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