Dosimetry-adjusted reactor physics parameters for pressure vessel neutron exposure assessment
The ASTM E706 master matrix standard describes a series of 20 American Society for Testing and Materials (ASTM) standard practices, guides, and methods for use in the prediction of neutron-induced changes in light water reactor (LWR) pressure vessel (PV) and support structure steels throughout a PV's service life. Some of these are existing ASTM standards, some are ASTM standards that have been modified, and some are new ASTM standards. These standards are periodically revised to assume their applicability during the 40-yr (32 effective full-power years) design license period for a nuclear power plant. They are now under review by two new ASTM plant life extension task groups: E10.05.11 on physics dosimetry and E10.02.11 on metallurgy. A brief review on the current application of these standards and a discussion of the status of work to verify the accuracy of derived physics-dosimetry parameter values is presented in this paper.
- OSTI ID:
- 5434100
- Report Number(s):
- CONF-881011-; CODEN: TANSA; TRN: 89-031413
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 57; Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC (USA), 30 Oct - 4 Nov 1988; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
BWR TYPE REACTORS
PRESSURE VESSELS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
ACCURACY
AGING
BENCHMARKS
DOSIMETRY
MECHANICAL STRUCTURES
NEUTRON FLUX
NEUTRON SPECTRA
NEUTRON TRANSPORT
REACTOR PHYSICS
REGULATIONS
SERVICE LIFE
US NRC
CONTAINERS
NATIONAL ORGANIZATIONS
NEUTRAL-PARTICLE TRANSPORT
PHYSICS
RADIATION EFFECTS
RADIATION FLUX
RADIATION TRANSPORT
REACTORS
SPECTRA
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WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
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210200 - Power Reactors
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360106 - Metals & Alloys- Radiation Effects