Experiment-specific analyses in support of code development
Abstract
Experiment-specific models have been developed since 1986 by Oak Ridge National Laboratory Boiling Water Reactor (BWR) severe accident analysis programs for the purpose of BWR experimental planning and optimum interpretation of experimental results. These experiment-specific models have been applied to large integral tests (ergo, experiments) which start from an initial undamaged core state. The tests performed to date in BWR geometry have had significantly different-from-prototypic boundary and experimental conditions because of either normal facility limitations or specific experimental constraints. These experiments (ACRR: DF-4, NRU: FLHT-6, and CORA) were designed to obtain specific phenomenological information such as the degradation and interaction of prototypic components and the effects on melt progression of control-blade materials and channel boxes. Applications of ORNL models specific to the ACRR DF-4 and KfK CORA-16 experiments are discussed and significant findings from the experimental analyses are presented. 32 refs., 16 figs.
- Authors:
- Publication Date:
- Research Org.:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Org.:
- USNRC
- OSTI Identifier:
- 6157226
- Report Number(s):
- CONF-901085-6
ON: DE91005908; TRN: 91-001714
- DOE Contract Number:
- AC05-84OR21400
- Resource Type:
- Conference
- Resource Relation:
- Conference: 7. international seminar on polymer physics: thin polymeric layers, Guentersberge (Germany, F.R.), 22-26 Oct 1990
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; BWR TYPE REACTORS; MELTDOWN; B CODES; CHEMICAL REACTION KINETICS; COMPUTER CODES; CONTROL ELEMENTS; CORIUM; EXPERIMENT PLANNING; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; OXIDATION; R CODES; REACTOR SAFETY; S CODES; STEAM; VALIDATION; ZIRCALOY; ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; ENERGY TRANSFER; FLUID MECHANICS; KINETICS; MECHANICS; PLANNING; REACTION KINETICS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 990200 - Mathematics & Computers
Citation Formats
Ott, L J. Experiment-specific analyses in support of code development. United States: N. p., 1990.
Web.
Ott, L J. Experiment-specific analyses in support of code development. United States.
Ott, L J. 1990.
"Experiment-specific analyses in support of code development". United States. https://www.osti.gov/servlets/purl/6157226.
@article{osti_6157226,
title = {Experiment-specific analyses in support of code development},
author = {Ott, L J},
abstractNote = {Experiment-specific models have been developed since 1986 by Oak Ridge National Laboratory Boiling Water Reactor (BWR) severe accident analysis programs for the purpose of BWR experimental planning and optimum interpretation of experimental results. These experiment-specific models have been applied to large integral tests (ergo, experiments) which start from an initial undamaged core state. The tests performed to date in BWR geometry have had significantly different-from-prototypic boundary and experimental conditions because of either normal facility limitations or specific experimental constraints. These experiments (ACRR: DF-4, NRU: FLHT-6, and CORA) were designed to obtain specific phenomenological information such as the degradation and interaction of prototypic components and the effects on melt progression of control-blade materials and channel boxes. Applications of ORNL models specific to the ACRR DF-4 and KfK CORA-16 experiments are discussed and significant findings from the experimental analyses are presented. 32 refs., 16 figs.},
doi = {},
url = {https://www.osti.gov/biblio/6157226},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1990},
month = {Mon Jan 01 00:00:00 EST 1990}
}