Water Reactor Safety Research Division quarterly progress report, January 1-March 31, 1980
Abstract
The Water Reactor Safety Research Programs Quarterly Report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: LWR Thermal Hydraulic Development, Advanced Code Evaluation, TRAC Code Assessment, and Stress Corrosion Cracking of PWR Steam Generator Tubing.
- Authors:
-
- comp.
- Publication Date:
- Research Org.:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- OSTI Identifier:
- 5320797
- Report Number(s):
- NUREG/CR-1506; BNL-NUREG-51218
ON: TI85015918
- DOE Contract Number:
- AC02-76CH00016
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; PWR TYPE REACTORS; STEAM GENERATORS; REACTOR SAFETY; RESEARCH PROGRAMS; STRESS CORROSION; WATER COOLED REACTORS; COMPUTER CODES; CRACKS; R CODES; T CODES; TUBES; BOILERS; CHEMICAL REACTIONS; CORROSION; REACTORS; SAFETY; VAPOR GENERATORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety
Citation Formats
Romano, A. J. Water Reactor Safety Research Division quarterly progress report, January 1-March 31, 1980. United States: N. p., 1980.
Web. doi:10.2172/5320797.
Romano, A. J. Water Reactor Safety Research Division quarterly progress report, January 1-March 31, 1980. United States. https://doi.org/10.2172/5320797
Romano, A. J. 1980.
"Water Reactor Safety Research Division quarterly progress report, January 1-March 31, 1980". United States. https://doi.org/10.2172/5320797. https://www.osti.gov/servlets/purl/5320797.
@article{osti_5320797,
title = {Water Reactor Safety Research Division quarterly progress report, January 1-March 31, 1980},
author = {Romano, A. J.},
abstractNote = {The Water Reactor Safety Research Programs Quarterly Report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: LWR Thermal Hydraulic Development, Advanced Code Evaluation, TRAC Code Assessment, and Stress Corrosion Cracking of PWR Steam Generator Tubing.},
doi = {10.2172/5320797},
url = {https://www.osti.gov/biblio/5320797},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jun 01 00:00:00 EDT 1980},
month = {Sun Jun 01 00:00:00 EDT 1980}
}
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