Developmental assessment of IFCI 6.0

Reed, A W; Young, M F; Schmidt, R C

Title: Developmental assessment of IFCI 6.0

Full Record
Other Related Research

Abstract

Version 6.0 of the IFCI code is being assessed by comparing predictions against the results of several experiments. Simulations of the first two of these experiments, MAGICO-701 and MIXA-6, have been completed with a reasonable level of success. Agreement with the MAGICO-701 experiment was good but was limited somewhat by the inherent problem of numerical diffusion. Results of the MIXA-6 calculations were comparable to those of CHYMES, but clearly suggested the need for an inter-cell radiation transport model in IFCI.

Authors:: Reed, A W; Young, M F; Schmidt, R C

Publication Date:: Fri Mar 01 00:00:00 EST 1996

Research Org.:: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Sponsoring Org.:: Nuclear Regulatory Commission, Washington, DC (United States)

OSTI Identifier:: 224970

Report Number(s):: SAND-96-0655C; CONF-960306-26
ON: DE96006987; TRN: 96:012142

DOE Contract Number:: AC04-94AL85000

Resource Type:: Conference

Resource Relation:: Conference: ICONE 4: ASME/JSME international conference on nuclear engineering, New Orleans, LA (United States), 10-13 Mar 1996; Other Information: PBD: [1996]

Country of Publication:: United States

Language:: English

Subject:: 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; FUEL-COOLANT INTERACTIONS; I CODES; MOLTEN SALT FUELED REACTORS; VERIFICATION; HEAT TRANSFER; HYDRAULICS; REACTOR PHYSICS; MOLTEN METAL-WATER REACTIONS

Citation Formats


                    Reed, A W, Young, M F, and Schmidt, R C. Developmental assessment of IFCI 6.0.  United States: N. p., 1996. 
        Web.

Copy to clipboard


                    Reed, A W, Young, M F, & Schmidt, R C. Developmental assessment of IFCI 6.0.  United States.

Copy to clipboard


                    Reed, A W, Young, M F, and Schmidt, R C. 1996.  
        "Developmental assessment of IFCI 6.0".  United States.  https://www.osti.gov/servlets/purl/224970.

Copy to clipboard


                    
@article{osti_224970,

  title        = {Developmental assessment of IFCI 6.0},

  author       = {Reed, A W and Young, M F and Schmidt, R C},

  abstractNote = {Version 6.0 of the IFCI code is being assessed by comparing predictions against the results of several experiments. Simulations of the first two of these experiments, MAGICO-701 and MIXA-6, have been completed with a reasonable level of success. Agreement with the MAGICO-701 experiment was good but was limited somewhat by the inherent problem of numerical diffusion. Results of the MIXA-6 calculations were comparable to those of CHYMES, but clearly suggested the need for an inter-cell radiation transport model in IFCI.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/224970},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Fri Mar 01 00:00:00 EST 1996},

  month        = {Fri Mar 01 00:00:00 EST 1996}

}

Copy to clipboard

Conference:

View Conference (0.76 MB)

Other availability

Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

Integrated Fuel-Coolant Interaction (IFCI 6.0) code. User`s manual

Technical Report Davis, F; Young, M

The integrated Fuel-Coolant interaction (IFCI) computer code is being developed at Sandia National Laboratories to investigate the fuel-coolant interaction (FCI) problem at large scale using a two-dimensional, four-field hydrodynamic framework and physically based models. IFCI will be capable of treating all major FCI processes in an integrated manner. This document is a product of the effort to generate a stand-alone version of IFCI, IFCI 6.0. The User`s Manual describes in detail the hydrodynamic method and physical models used in IFCI 6.0. Appendix A is an input manual, provided for the creation of working decks.
https://doi.org/10.2172/10147584

Full Text Available
IFCI 7.0 Models and Correlations

Technical Report Reed, A; Schmidt, R; Young, M

The Integrated Fuel-Coolant Interaction Code (IFCI) is a best-estimate computer program for analysis of phenomena related to mixing of molten nuclear reactor core material with reactor coolant (water). The stand-alone version of the code, IFCI 7.0, has been designed for analysis of small- and intermediate-scale experiments in order to gain insight into the physics (including scaling effects) of molten fuel-coolant interactions. The code's methods, models, and correlations are being assessed. This report describes the flow regime, friction factor, and heat-transfer models used in the current version of IFCI (IFCI 7.0).
https://doi.org/10.2172/7685

Full Text Available
Assessment of models for steam release from concrete and implications for modeling corium behavior in reactor cavities

Conference Washington, K; Carroll, D

Models for concrete outgassing have been developed and incorporated into a developmental version of the CONTAIN code for the assessment of corium behavior in reactor cavities. The resultant code, referred to as CONTAIN/OR in order to distinguish it from the released version of CONTAIN, has the capability to model transient heat conduction and concrete outgassing in core-concrete interaction problems. This study focused on validation and assessment of the outgassing model through comparisons with other concrete response codes. In general, the model is not mechanistic; however, there are certain important processes and feedback effects that are treated rigorously. The CONTAIN outgassingmore »« less
Secondary Electrons from Water Vapor with the Impact of 6.0 MeV/u He2+ Ions: Atomic Data and their Application to Biomedical Investigations

Journal Article Sato, Y; Soga, F; Ohsawa, D; ... - AIP Conference Proceedings

We measured the energy and angular distributions (7 eV-10 keV and 20 degree sign -160 degree sign ) of secondary electrons produced in collisions of 6.0 MeV/u He2+ ions with water vapor. Binary-encounter collision peaks were clearly observed at the calculated energies at angles of <90 degree sign , as well as the K-LL Auger peak of oxygen at about 500 eV for all angles. From these measurements, the doubly differential cross sections (DDCS) of electron emissions were deduced with an estimated uncertainty of {+-}13%. The energy distribution (SDCS) was also obtained by integrating the DDCS values with respect tomore »« less
https://doi.org/10.1063/1.1944700
Cross-section measurement and analysis for the {sup 149}Sm(n,alpha){sup 146}Nd reaction at 6.0 MeV

Journal Article Gledenov, Yu; Sedysheva, M; Guohui, Zhang; ... - Physical Review. C, Nuclear Physics

We have measured the {sup 149}Sm(n,alpha){sup 146}Nd cross section at 6.0 MeV to be 0.12+-0.018 mb. This is the first reported result for this cross section in the MeV region and so should be helpful for constraining nuclear data evaluations (which differ by a factor of 40 for this reaction at this energy) and for testing and improving nuclear models. The experiment was performed at the at the 4.5-MV Van de Graaff accelerator of Peking University. Neutrons were produced via the {sup 2}H(d,n){sup 3}He reaction using a deuterium gas target, and absolute neutron flux was determined with a small {supmore »« less
https://doi.org/10.1103/PHYSREVC.82.014601

Similar Records