Use of separate-effects experiments in verification of system thermal-hydraulics
Description
In recent years, a number of advanced, best-estimate systems codes such as TRAC and RELAP5 have been developed in order to accurately predict the consequences of various postulated accidents and transients in Light Water Reactor (LWR) systems. Although these codes had to go through some verification or assessment during the developmental stage, it has been recognized that an independent assessment of these codes is necessary before they should be applied to any decision making process. The USNRC is, therefore, sponsoring such efforts at several national laboratories including BNL. The overall assessment matrix includes separate-effects, integral and plant tests. However, this paper will focus on how the separate-effects tests can be utilized in verifying the thermal-hydraulic models that control the various stages of postulated accidents and/or transients in a LWR system
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82010919.Files
14723992.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- BNL-NUREG--30779
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 6 - 11 Jun 1982.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14723992
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; 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 CALCULATIONS; HEAT TRANSFER; HYDRAULICS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-820609--18.