Actions for Reactor Safety Research [electronic resource] : Semiannual report, January-June 1986 Reactor Safety Research Program
Reactor Safety Research [electronic resource] : Semiannual report, January-June 1986 Reactor Safety Research Program
- Published
- Albuquerque, N.M. : Sandia National Laboratories, 1987.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Additional Creators
- Sandia National Laboratories and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions.
- Report Numbers
- E 1.99:nureg/cr-4805/1
E 1.99: sand-86-2752/1
sand-86-2752/1
nureg/cr-4805/1 - Subject(s)
- Other Subject(s)
- Bwr Type Reactors
- Reactor Safety
- Lmfbr Type Reactors
- Pwr Type Reactors
- Research Programs
- C Codes
- Computerized Simulation
- Containment
- Fission Products
- Flames
- H Codes
- Hydrogen
- M Codes
- Radioactive Effluents
- Radioactivity Transport
- Reactor Accidents
- Reactor Components
- Reactor Cooling Systems
- Reporting Requirements
- V Codes
- Accidents
- Breeder Reactors
- Computer Codes
- Cooling Systems
- Elements
- Energy Systems
- Epithermal Reactors
- Fast Reactors
- Fbr Type Reactors
- Isotopes
- Liquid Metal Cooled Reactors
- Materials
- Nonmetals
- Radioactive Materials
- Radioactive Wastes
- Reactors
- Safety
- Simulation
- Wastes
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
05/01/1987.
"nureg/cr-4805/1"
" sand-86-2752/1"
"TI87012056"
Not Available. - Funding Information
- AC04-76DP00789
View MARC record | catkey: 14370337