Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Retrospective Reactor Dosimetry for Neutron Fluence, Helium, and Boron Measurements

Conference ·
OSTI ID:15016528
Neutron fluences can be measured and radiation damage parameters determined by analyzing the neutron reaction products in very small samples removed from components of an operating power research reactor. This process, known as retrospective reactor dosimetry, provides precise neutron exposure parameters for establishing or validating calculations of neutron fluences, helium generation, and radiation damage to reactor materials. Correlation of the neutron fluence and helium data helps to establish and validate models of radiation damage and helium production that are needed to address important issues such as irradiation assisted stress corrosion cracking, void swelling, and weld repair of cracks. Results are presented for samples recently obtained from several operating reactors.
Research Organization:
Pacific Northwest National Lab., Richland, WA (US)
Sponsoring Organization:
US Department of Energy (US)
DOE Contract Number:
AC05-76RL01830
OSTI ID:
15016528
Report Number(s):
PNNL-SA-38351
Country of Publication:
United States
Language:
English