Published September 1995
| Version v1
Report
Restricted
Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Volume 1, Sessions 1-5
Creators
- Block, R.C.1
- Feiner, F. (Producer)1
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology
- American Inst. of Chemical Engineers, New York, NY (United States)
- American Society of Mechanical Engineers, New York, NY (United States)
- Canadian Nuclear Society, Toronto, ON (Canada)
- Japan Society of Multiphase Flow, Osaka (Japan)
- 1. American Nuclear Society, La Grange Park, IL (United States)
Description
This document, Volume 1, includes papers presented at the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-7) September 10--15, 1995 at Saratoga Springs, N.Y. The following subjects are discussed: Progress in analytical and experimental work on the fundamentals of nuclear thermal-hydraulics, the development of advanced mathematical and numerical methods, and the application of advancements in the field in the development of novel reactor concepts. Also combined issues of thermal-hydraulics and reactor/power-plant safety, core neutronics and/or radiation. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI95017077; NTIS; GPO.
Files
Additional details
Publishing Information
- Imprint Pagination
- 862 p.
- Report number
- NUREG/CP--0142-Vol.1
Conference
- Title
- 7. international meeting on nuclear reactor thermal hydraulics.
- Dates
- 10-15 Sep 1995.
- Place
- Saratoga, NY (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27008526
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; FUEL ASSEMBLIES; HEAT TRANSFER; HYDRAULICS; LEADING ABSTRACT; LMFBR TYPE REACTORS; MEETINGS; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR INSTRUMENTATION; REACTOR KINETICS; REACTOR SAFETY; TRANSIENTS; TWO-PHASE FLOW
- Descriptors DEC
- ABSTRACTS; BREEDER REACTORS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; KINETICS; LIQUID METAL COOLED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- CONF-950904--Vol.1.