Fluence-to-dose equivalent conversion factors for polyethylene-moderated {sup 252}Cf
Conference
·
OSTI ID:10158649
- Pacific Northwest Lab., Richland, WA (United States)
- Los Alamos National Lab., NM (United States)
Neutron measurements and calculations were conducted to characterize the polyethylene-moderated {sup 252}Cf source at Oak Ridge National Laboratory`s Radiation Calibration Laboratory (RADCAL). The 12-inch-diameter polyethylene sphere produces a highly scattered neutron spectrum which is more representative of most radiation fields found in the workplace than the D{sub 2}O-moderated {sup 252}Cf neutron spectrum typically used for dosimeter calibration. However, the energy-dependent fluence and dose equivalent must be well known before using such a source for radiation protection purposes. The measurements and calculations were performed as independent checks of the desired quantities which were the flux, the absorbed dose rate, the dose equivalent rate, and the average energy. These quantities were determined for the polyethylene sphere with and without an outer cadmium shell and compared with a D{sub 2}O-moderated {sup 252}Cf source.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10158649
- Report Number(s):
- PNL-SA--23615; CONF-940424--36; ON: DE94013348
- Country of Publication:
- United States
- Language:
- English
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· Transactions of the American Nuclear Society; (United States)
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