SOFIRE II user report

Beiriger, P.; Hopenfeld, J.; Silberberg, Martin; Johnson, R.P.; Baurmash, L.; Koontz, R.L.

doi:10.2172/4490831

Cited by 22 publications

(8 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…To verify that the newly compiled version of the SOFIRE-II code ONE CELL version produces the correct results, the calculation of the test problem was run The input and output of the test problem were provided with the code; the results of the test problem were also plotted in the code report [1].…”

Section: Verification Of Test Problem Resultsmentioning

confidence: 99%

“…The input variable for additional thermal radiation across the gap is set equal to unity. The meaning of the thermal radiation input variable is not discussed in the code user report [1]. If the variable for thermal radiation across the gap is meant to account for the emissivities of the liner and concrete surfaces facing each other, then the calculations below which set the variable equal to unity overestimates the effects of thermal radiation from the steel liner to the concrete.…”

Section: Verification Of Test Problem Resultsmentioning

confidence: 99%

“…As delivered, the code actually consists of the two versions discussed in the user report [1], SOFIRE II ONE CELL and SOFIRE II TWO CELL. The former has been implemented at ANL.…”

Section: Sofire-ii Code Implementation At Anlmentioning

confidence: 99%

See 2 more Smart Citations

Sodium pool fire phenomena, sodium pool fire modeling in SOFIRE II, and SOFIRE II calculations for the AFR-100

Sienicki¹,

Moisseytsev²

2012

View full text Add to dashboard Cite

The SOFIRE II computer code for the calculation of sodium pool fires has been obtained from the Reactor Safety Information Computational Center and the SOFIRE II ONE CELL version has been implemented at Argonne National Laboratory (ANL). A critical review of literature relevant to sodium pool fires has been carried out with the objectives of understanding sodium pool fire phenomena and how well specific phenomena are modeled or neglected in SOFIRE II. Significant predictions about sodium pool fires can be made on the basis of first principles analyses alone making use of the existing experiment database and knowledge base. In implementing SOFIRE II ONE CELL, minor modifications were necessary to compile and execute the code on a personal computer (PC) and to verify the results of the test case problem. The code was applied to the AFR-100 Sodium-Cooled Fast Reactor (SFR) design to calculate a sodium pool fire following a postulated failure of the sodium storage vessel of one of the four intermediate sodium heat transport circuits and the subsequent release of sodium onto the floor of the steel-lined compartment in which the sodium storage vessel is located. SOFIRE II calculates that only a small fraction of the released sodium burns due to the rapid consumption of the available oxygen inside of the closed compartment. The preliminary results demonstrate the effects of the heat sinks provided by the compartment floor, walls, and ceiling in reducing the temperature of the sodium pool with time.

show abstract

Section: Verification Of Test Problem Resultsmentioning

confidence: 99%

Section: Verification Of Test Problem Resultsmentioning

confidence: 99%

See 1 more Smart Citation

Sodium pool fire phenomena, sodium pool fire modeling in SOFIRE II, and SOFIRE II calculations for the AFR-100

Sienicki¹,

Moisseytsev²

2012

View full text Add to dashboard Cite

show abstract

“…However, the ranking of these phenomena is judged to be 'M' instead of 'H,' taking into account the fact that the computational models of pool combustion and heat transfer in two codes have already been assessed to be adequate (13), (7) . Further, the similar pool fire and heat transfer models have been validated as those of other computer codes by many studies (14), (2) since the 1970's. "(9) Aerosols generation from pool" is given as an input parameter in the current sodium fire evaluation tools.…”

Section: Pirt For Temperature Increase In Floor Structurementioning

confidence: 99%

Development of PIRT and Assessment Matrix for Verification and Validation of Sodium Fire Analysis Codes

Ohno

Ohshima

Tajima³

et al. 2012

JPES

View full text Add to dashboard Cite

Thermodynamic consequence in liquid sodium leak and fire accident is one of the important issues to be evaluated when considering the safety aspect of fast reactor plant building. The authors are therefore initiating systematic verification and validation (V&V) activity to assure and demonstrate the reliability of numerical simulation tool for sodium fire analysis. The V&V activity is in progress with the main focuses on already developed sodium fire analysis codes SPHINCS and AQUA-SF. The events to be evaluated are hypothetical sodium spray, pool, or combined fire accidents followed by thermodynamic behaviors postulated in a plant building. The present paper describes that the 'Phenomena Identification and Ranking Table (PIRT)' is developed at first for clarifying the important validation points in the sodium fire analysis codes, and that an 'Assessment Matrix' is proposed which summarizes both separate effect tests and integral effect tests for validating the computational models or whole code for important phenomena. Furthermore, the paper shows a practical validation with a separate effect test in which the spray droplet combustion model of SPHINCS and AQUA-SF predicts the burned amount of a falling sodium droplet with the error mostly less than 30%.

show abstract

“…CONTAIN-LMR has models to describe sodium pool fires and sodium spray fires. The sodium pool fire model is taken from SOFIRE II (Beiriger 1973). The sodium-concrete interactions are based upon the SLAM model (Suo-Anttila 1983).…”

Section: Model Developmentmentioning

confidence: 99%

Metal fire implications for advanced reactors. Part 1, literature review.

Nowlen¹,

Radel²,

Hewson³

et al. 2007

View full text Add to dashboard Cite

Public safety and acceptance is extremely important for the nuclear power renaissance to get started. The Advanced Burner Reactor and other potential designs utilize liquid sodium as a primary coolant which provides distinct challenges to the nuclear power industry. Fire is a dominant contributor to total nuclear plant risk events for current generation nuclear power plants. Utilizing past experience to develop suitable safety systems and procedures will minimize the chance of sodium leaks and the associated consequences in the next generation. An advanced understanding of metal fire behavior in regards to the new designs will benefit both science and industry. This report presents an extensive literature review that captures past experiences, new advanced reactor designs, and the current state-of-knowledge related to liquid sodium combustion behavior.3

show abstract

SOFIRE II user report

Cited by 22 publications

References 0 publications

Sodium pool fire phenomena, sodium pool fire modeling in SOFIRE II, and SOFIRE II calculations for the AFR-100

Sodium pool fire phenomena, sodium pool fire modeling in SOFIRE II, and SOFIRE II calculations for the AFR-100

Development of PIRT and Assessment Matrix for Verification and Validation of Sodium Fire Analysis Codes

Metal fire implications for advanced reactors. Part 1, literature review.

Contact Info

Product

Resources

About