Evaluation of integral continuing experimental capability (CEC) concepts for light water reactor research: PWR scaling concepts
Description
In this report reactor transients and thermal-hydraulic phenomena of importance (based on probabilistic risk assessment and the International Code Assessment Program) to reactor safety were examined and identified. Established scaling methodologies were used to develop potential concepts for integral thermal-hydraulic testing facilities. Advantages and disadvantages of each concept are evaluated. Analysis is conducted to examine the scaling of various phenomena in each of the selected concepts. Results generally suggest that a facility capable of operating at typical reactor operating conditions will scale most phenomena reasonably well. Although many phenomena in facilities using Freon or water at nontypical pressure will scale reasonably well, those phenomena that are heavily dependent on quality (heat transfer or critical flow for example) can be distorted. Furthermore, relation of data produced in facilities operating with nontypical fluids or at nontypical pressures to large plants will be a difficult and time consuming process
Availability note (English)
Available from NTIS, PC A10/MF A01 - GPO as TI87007513.Files
19033085.pdf
Files
(7.4 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:800c031e72fac8e38c132bf987ad3aa8
|
7.4 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 213 p.
- Report number
- NUREG/CR--4824
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19033085
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ATWS; COMPUTER CALCULATIONS; DYNAMICS; FREONS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; LOSS OF FLOW; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SCALING LAWS; TEST FACILITIES; TRANSIENTS; TWO-PHASE FLOW; WATER; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DESIGN BASIS ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HYDROGEN COMPOUNDS; MECHANICS; ORGANIC COMPOUNDS; ORGANIC HALOGEN COMPOUNDS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SOLVENTS; THERMAL REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EGG--2494.