Radiation Dose Rates from UO2-PuO2 Thermal Reactor Fuels
| Autor: | D. W. Brite, L. W. Brackenbush, L. L. Nichols, R. C. Smith, L. G. Faust |
|---|---|
| Rok vydání: | 1972 |
| Předmět: |
Nuclear and High Energy Physics
Neutron dose Fabrication Materials science 020209 energy Nuclear engineering Radiation dose Radiochemistry chemistry.chemical_element 02 engineering and technology Neutron radiation Condensed Matter Physics Plutonium 020303 mechanical engineering & transports Radiation shielding 0203 mechanical engineering Nuclear Energy and Engineering chemistry Thermal 0202 electrical engineering electronic engineering information engineering Dose rate |
| Zdroj: | Nuclear Technology. 15:249-256 |
| ISSN: | 1943-7471 0029-5450 |
| DOI: | 10.13182/nt72-a31149 |
| Popis: | Gamma and neutron radiation dose rates from various experimental fuel assemblies and from full-size commercial BWR and PWR power reactor fuel assemblies containing UO2-PuO2 fuel with high exposure plutonium were measured. Maximum gamma and neutron dose rates encountered at 61-cm distance from the surfaces of the fuel assemblies were 6.5 mR/h and 25 mrem/h, respectively. It is concluded that commercial reactor operators can handle fuel assemblies containing high exposure plutonium without excessive personnel exposure and with a minimum of special handling procedures. However, radiation shielding for some fuel fabrication steps will be necessary with plutonium of the type expected to become available during the late 1970s. |
| Databáze: | OpenAIRE |
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