ASTM STP 1398 Reactor Dosimetry: Radiation Metrology and Assessment
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Williams JG
This STP contains papers presented at the Tenth International Symposium on Reactor Dosimetry held in September, 1999. The symposium was sponsored by the ASTM Committee E-10 on Nuclear Technology and Applications.
Following the three keynote papers, the rest of the papers in the STP are grouped under the headings
- Dosimetry for Power Reactor Surveillance
- Dosimetry for Test reactors and Accelerator Sources
- Benchmarks and Inter-comparisons
- Cross Sections and Nuclear Data
- Calculations and Adjustment Methods
- Damage Correlations and Damage Dosimetry
- Experimental Techniques
Specific topics addressed by papers in this publication include:
- Dosimetry
- library benchmark
- surveillance capsule
- pressure vessel
- PWR
- aging reactor vessel
- radiation embrittlement
- upper shelf energy
- pressurized thermal shock
- PV surveillance
- measurement of neutron flux distribution
- decommissioning
- ENDF/B-VI data
- neutron dosimetry, Monte Carlo, MCBEND
- activation of concrete in walls
- concrete aging
- concrete water loss
- neutron dose rate measurement
- Boron Neutron Capture Therapy (BNCT)
- TRIGA reactors
- Fe-filtered neutrons
- fast neutron irradiation facility (FNI)
- pellet/clad interaction (PCI)
- high energy neutron dosimetry application
- High Flux Beam Reactor (HFBR)
- Medical Research Reactor (BMRR)
- multi-wire activation method
- 3D neutron transport calculations
- fission power determination
- helium accumulation
- multi-moderator neutron spectrometer
- rector pressure vessel (RPV) surveillance
- VENUS experiment
- absolute leakage neutron spectrum
- Adjustment of the U Fission Spectrum
- LEPRICON
- Induced Activity Estimation method for PWR containment
- radiation hardening
- Embrittlement Data Base (EDB)
- neutron spectrometer
- HPGe detector
- measurement of the boron concentration