Jove
Visualize
Contact Us
JoVE
x logofacebook logolinkedin logoyoutube logo
ABOUT JoVE
OverviewLeadershipBlogJoVE Help Center
AUTHORS
Publishing ProcessEditorial BoardScope & PoliciesPeer ReviewFAQSubmit
LIBRARIANS
TestimonialsSubscriptionsAccessResourcesLibrary Advisory BoardFAQ
RESEARCH
JoVE JournalMethods CollectionsJoVE Encyclopedia of ExperimentsArchive
EDUCATION
JoVE CoreJoVE BusinessJoVE Science EducationJoVE Lab ManualFaculty Resource CenterFaculty Site
Terms & Conditions of Use
Privacy Policy
Policies

Related Experiment Videos

Nuclear accident dosimetry intercomparison studies.

C S Sims1

  • 1Oak Ridge National Laboratory, TN 37831-6379.

Health Physics
|September 1, 1989
PubMed
Summary

Nuclear accident dosimetry intercomparison studies since 1965 provided crucial data on neutron and gamma-ray dosimetry systems. While many neutron dose measurements met accuracy guidelines, gamma dose measurements showed lower accuracy rates.

Related Concept Videos

You might also read

Related Articles

Articles linked to this work by shared authors, journal, and citation graph.

Sort by
Same author

NRC regulation of DOE nuclear safety: an observation and some questions concerning radiation doses.

Health physics·1997
Same author

A proposed four-element neutron-photon-beta thermoluminescence dosimeter.

Health physics·1992
Same author

Neutron dosimetric quantities for several radioisotopic neutron sources.

Health physics·1992
Same author

Summary statements from the Third Conference on Radiation Protection and Dosimetry.

Health physics·1992
Same author

Modification of neutron-induced hematopoietic effects by chemical radioprotectors.

International journal of radiation oncology, biology, physics·1992
Same author

Summary statements from the Second Conference on Radiation Protection and Dosimetry.

Health physics·1989

Area of Science:

  • Health Physics
  • Radiation Detection and Measurement
  • Nuclear Safety

Background:

  • Since 1965, Oak Ridge National Laboratory's Health Physics Research Reactor hosted 22 nuclear accident dosimetry intercomparison studies.
  • These studies involved 62 organizations, simulating 69 criticality accidents with diverse neutron energy spectra.

Purpose of the Study:

  • To provide a platform for discussing criticality accident dosimetry.
  • To enable organizations to test neutron and gamma-ray dosimetry systems under simulated accident conditions.
  • To compare measurement results against reference values and other participants' data.

Main Methods:

  • Simulated criticality accidents using a fast-pulse reactor.
  • Neutron dosimetry primarily utilized activation foils, thermoluminescent dosimeters (TLDs), and blood sodium activation.
  • Gamma dose measurements employed TLDs, radiophotoluminescent glass, and film dosimeters.

Main Results:

  • A total of 2,289 dose measurements (1,311 neutron, 978 gamma) were recorded across simulated accidents.
  • Neutron doses ranged from 0.2-8.5 Gy; gamma doses ranged from 0.1-2.0 Gy.
  • Approximately 68% of neutron measurements met the +/- 25% accuracy guideline, while 52% of gamma measurements met the +/- 20% criterion.

Conclusions:

  • The intercomparison studies have been vital for advancing nuclear accident dosimetry.
  • Results indicate a need for improved accuracy in gamma dosimetry for criticality accidents.
  • Continuous participation and comparison are essential for refining dosimetry techniques and ensuring personnel safety.

Related Experiment Videos