User's manual for CONTAIN 1.1: A computer code for severe nuclear reactor accident containment analysis

Murata, Kazuya; Carroll, D. E.; Washington, K.E.; Gelbard, Fred; Valdez, Greg D.; Williams, D. C.; Bergeron, K.D.

doi:10.2172/5199155

Cited by 30 publications

(3 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…These include SOFIRE-II [323] and NACOM [324], which are no longer supported. The models within these codes were later integrated in CONTAIN-LMR 1.0 [325] and have now also been added to MELCOR 2.2 [83]. Although these codes include the formation of sodium oxide aerosols, they do not model the release of any radionuclides contained with the sodium itself or the associated structure (such as a cesium trap).…”

Section: Sodium Firesmentioning

confidence: 99%

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Clark¹,

Luxat²,

Higgins³

et al. 2020

View full text Add to dashboard Cite

Section: Sodium Firesmentioning

confidence: 99%

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Clark¹,

Luxat²,

Higgins³

et al. 2020

View full text Add to dashboard Cite

“…SPECTRA can comprehensively simulate in-and ex-vessel phenomena during a severe accident (SA) in an SFR. In conventional SA evaluation for an SFR, multiple numerical tools were employed, such as SAS4A (Tentner et al, 1985) for the initiation phase of core melting, SIMMER (Kondo et al, 1992) for the relocation and cooling phases, and CONTAIN-LMR (Murata et al, 1989) for the ex-vessel phenomena, respectively. This evaluation schema requires code-to-code connections in the case of a sequential event.…”

Section: Introductionmentioning

confidence: 99%

Model integration of the ex-vessel modules for the SFR safety analysis code SPECTRA

AOYAGI,

MAKINO,

OHKI

et al. 2024

Mechanical Engineering Journal

View full text Add to dashboard Cite

The SPECTRA code has been developed as an integrated safety analysis tool for comprehensive analyses of inand ex-vessel phenomena during a severe accident (SA) in a sodium-cooled fast reactor (SFR). The individual modules, such as sodium fire and sodium-concrete reaction, have been implemented into SPECTRA to simulate specific phenomena in an accident of SFRs. However, SPECTRA has no capability for the overlapped event involving sodium fire and sodium-concrete reaction in the same compartment because the sodium pool and the floor concrete are modeled in each module independently. The capability of SPECTRA is enhanced by integrating the analyses of sodium pool fire and concrete ablation for overlapped events of the ex-vessel phenomena. A new shared module for the sodium pool and floor concrete region, named "PFC module" was introduced in the previous study. The sodium fire module is connected to the PFC module in this study. The integrated model is validated through the benchmark analysis of the F7-1 pool fire experiment. The calculation results of the temperature and combustion rate show good agreement with the experimental result. A demonstration analysis is also conducted for an overlapped event of the ex-vessel phenomena including both concrete ablation and sodium pool fire. SPECTRA can simulate a reasonable heat and mass transfer behavior during the overlapped event.

show abstract

“…Rosin and Rammler (1933) has developed the Rosin-Rammler empirical relation based on the droplet size distribution in the breakup process of pulverized coal and cement slurry, which can be regarded as a special form of expression of the Nukiyama-Tanasawa model. In addition, the Nukiyama-Tanasawa model, obtained by measuring the droplet size distribution, is adopted in the sodium spray and fire analysis programs of NACOM (Tsai, 1980), CONTAIN-LMR (Murata et al, 1993), and SPHINCS (Yamaguchi and Tajima, 2002). However, the model relies heavily on the determination of the average droplet size.…”

Section: Introductionmentioning

confidence: 99%

Semi-Empirical Model of Droplet Size Distribution From the Maximum Entropy Principle in Sodium Spray

Zou

Tong

et al. 2022

Front. Energy Res.

View full text Add to dashboard Cite

When a sodium leakage accident occurs in the sodium-cooled fast reactor, the leaked sodium reacts violently with the air in the form of droplets, resulting in the phenomenon of sodium spray fire. The droplet size distribution formed by liquid sodium injection is the key factor affecting the accident analysis of sodium spray fire. Based on the theory of the maximum entropy principle, a semi-empirical model of sodium spray droplet size distribution is constructed, which is constrained by the mass equation or the momentum equation with viscous resistance, respectively. Based on the existing liquid fuel droplet size distribution experiment results and the sodium spray fire experiment results, the semi-empirical model is verified, which shows that the prediction result with the semi-empirical model constrained by the momentum equation is in good agreement with the experimental result with the error of about 20%. Furthermore, the proposed sodium spray droplet model is compared with other models of the empirical model, the semi-empirical model, and the model based on the maximum entropy principle constrained by the simplified mass equation. The simulation result with the proposed model matches the experimental data better with minor error.

show abstract

User's manual for CONTAIN 1.1: A computer code for severe nuclear reactor accident containment analysis

Cited by 30 publications

References 0 publications

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Survey and Assessment of Computational Capabilities for Advanced (Non-LWR) Reactor Mechanistic Source Term Analysis.

Model integration of the ex-vessel modules for the SFR safety analysis code SPECTRA

Semi-Empirical Model of Droplet Size Distribution From the Maximum Entropy Principle in Sodium Spray

Contact Info

Product

Resources

About