title: Radiological characterization of the pressure vessel internals of the BNL High Flux Beam Reactor.
abstract: In preparation for the eventual decommissioning of the High Flux Beam Reactor after the permanent removal of its fuel elements from the Brookhaven National Laboratory, measurements and calculations of the decay gamma-ray dose-rate were performed in the reactor pressure vessel and on vessel internal structures such as the upper and lower thermal shields, the Transition Plate, and the Control Rod blades. Measurements of gamma-ray dose rates were made using Red Perspex polymethyl methacrylate high-dose film, a Radcal "peanut" ion chamber, and Eberline's RO-7 high-range ion chamber. As a comparison, the Monte Carlo MCNP code and MicroShield code were used to model the gamma-ray transport and dose buildup. The gamma-ray dose rate at 8 cm above the center of the Transition Plate was measured to be 160 Gy h (using an RO-7) and 88 Gy h at 8 cm above and about 5 cm lateral to the Transition Plate (using Red Perspex film). This compares with a calculated dose rate of 172 Gy h using Micro-Shield. The gamma-ray dose rate was 16.2 Gy h measured at 76 cm from the reactor core (using the "peanut" ion chamber) and 16.3 Gy h at 87 cm from the core (using Red Perspex film). The similarity of dose rates measured with different instruments indicates that using different methods and instruments is acceptable if the measurement (and calculation) parameters are well defined. Different measurement techniques may be necessary due to constraints such as size restrictions.
authors.affiliation: Brookhaven National Laboratory, Upton, NY 11973-5000, USA. holden@bnl.gov
authors.forename: Norman E
authors.initials: NE
authors.lastname: Holden
authors.forename: Richard N
authors.initials: RN
authors.lastname: Reciniello
authors.forename: Jih-Perng
authors.initials: JP
authors.lastname: Hu
mesh_terms: D003666:Decontamination / Q000379:methods* / Q000592:standards*; D004866:Equipment Contamination / Q000517:prevention & control*; D019544:Equipment Failure Analysis / Q000379:methods / Q000592:standards; D004869:Equipment Safety / Q000379:methods / Q000592:standards; D009688:Nuclear Reactors / Q000295:instrumentation* / Q000592:standards*; D011312:Pressure; D011874:Radiometry / Q000379:methods* / Q000592:standards*; D015203:Reproducibility of Results; D012680:Sensitivity and Specificity; D014481:United States