Dose evaluation in criticality accident conditions using transient critical facilities fueled with a fissile solution.
Neutron dose measurement and evaluation techniques in criticality accident conditions using a thermo luminescence dosemeter (TLD) was studied at the Transient Experiment Critical Facility (TRACY) of Japan Atomic Energy Research Institute (JAERI). In the present approach, the absorbed dose is derived from the ambient dose equivalent measured with a TLD, using the appropriate conversion factor given by computation. Using this technique, the neutron dose around the SILENE reactor of the Institute for Radioprotection and Nuclear Safety (IRSN) of France was measured in the Accident Dosimetry Intercomparison Exercise (June 10-21, 2002) organized by OECD/NEA and IRSN. In this exercise, the gamma dose was also measured with a TLD. In this report, measurements and evaluation results at TRACY and SILENE are presented.
Nakamura
T
T
Japan Atomic Energy Research Institute, Shirakata-Shirane 2-4, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195, Japan. takemi99@popsut.tokai.jaeti.go.jp
Tonoike
K
K
Miyoshi
Y
Y
D000465:Algorithms; D001822:Body Burden; D006801:Humans; D009502:Neutrons; D009680:Nuclear Fission; D009688:Nuclear Reactors; D011785:Quality Assurance, Health Care / Q000379:methods; D011829:Radiation Dosage; D011835:Radiation Protection / Q000295:instrumentation / Q000379:methods*; D018788:Radioactive Hazard Release; D012015:Reference Standards; D012062:Relative Biological Effectiveness; D015203:Reproducibility of Results; D018570:Risk Assessment / Q000379:methods*; D012307:Risk Factors; D017751:Safety Management / Q000379:methods; D012680:Sensitivity and Specificity; D013819:Thermoluminescent Dosimetry / Q000295:instrumentation / Q000379:methods*