Exerimental method and preliminary studies of the passive containment water film evaporation mass transfer
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,
Abstract
For larger containments and higher operation parameters, characteristics of the outside cooling of the PCCS are very important for the analysis on the containment integrity. A preliminary analysis was made and a four-step experimental method was used to numerically analyze the falling water film evaporation for the advanced passive containment. Then, the water flow stability along the outside wall of the containment was studied. The results fit well with those correlations without airflow when the air velocity is less than 5.0 m/s. However, when the air velocity is larger than 5.0 m/s, the influence of the air velocity on the water film will appear and the mean water film thickness will be thicker. Based on the prototype operation parameters, experimental studies were carried and the results were compared with the Dittus-Boelter correlation within the operation ranges. A modification factor was proposed for the conservative application of this correlation for nuclear safety analysis.
Abstract
Für größere Containments und höhere Betriebsparameter sind die Eigenschaften der Außenkühlung des passiven Einschluss-Kühlsystems (PCCS) sehr wichtig für die Analyse der Containment Integrität. Eine vorläufige Analyse wurde durchgeführt und eine vierstufige experimentelle Methode wurde verwendet um die Wasserfilmverdampfung für das fortgeschrittene passive Containment numerisch zu analysieren. Dann wurde die Wasserströmungsstabilität entlang der äußeren Containment-Wand untersucht. Die Ergebnisse passen gut zu den Korrelationen ohne Luftströmung bei Luftgeschwindigkeiten kleiner als 5.0 m/s. Bei höheren Luftgeschwindigkeiten beeinflusst die Luftströmung den Wasserfilm und die mittlere Wasserfilmdicke erhöht sich. Auf der Grundlage der Betriebsparameter des Prototyps wurden experimentelle Studien durchgeführt und die Ergebnisse mit der Dittus-Boelter Korrelation verglichen. Ein Anpassungsfaktor wird vorgeschlagen für eine konservative Anwendung dieser Korrelation bei der nuklearen Sicherheitsanalyse.
Acknowledgements
The project was financially supported by the National Science and Technology Major Project of the Ministry of Science and Technology of China (No. 2011ZX06002-005). We acknowledge the efforts from anonymous reviewers for the significant amount of edits and suggestions.
Greek symbols
- d
wall thickness, m
- D
difference, –
- l
thermal conductivity, W/m-K
- G
water film line rate, kg/m-s
- rb
bulk water vapor density, kg/m3
- rv
water vapor density at interface, kg/m3
Nomenclature Roman Symbols
- D
water vapor-air mass diffusivity coefficient, m2/s
- hfg
vaporization heat, kJ/kg
- L
length of the test section, m
- ma
airside water vapor increment, kg/s
- me
mean water evaporation, kg/s
- mw
water film side water vapor decrement, kg/s
- qa
convective and evaporation heat flux, W/m2
- qc
convective heat flux from Colburn correlation, W/m2
- qe
evaporation heat flux, W/m2
- qr
radiation heat flux, W/m2
- qt
total heat flux from hot wall, W/m2
- Re
Reynolds number, –
- RHb
bulk air relative humidity, –
- ub
bulk air velocity, m/s
- tb
bulk air temperature, 8C
- tw
water temperature
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Books · Bücher
Joint Radiation Emergency Management Plan of the International Organizations. IAEA EPR-JPLAN (2017), Published by the International Atomic Energy Agency 2017, 48 pp., 978-92-0-101017-9, 48 EUR
The Joint Plan describes the arrangements of the participating organizations for responding to a nuclear or radiological emergency irrespective of its cause and the measures for developing, maintaining, exercising and improving these arrangements. The Joint Plan does not include detailed procedures for its implementation. Although the Joint Plan may refer to international organizations other than those participating, these references are only understandings by the participating organizations and do not necessarily represent the understandings of those not participating in the Joint Plan.
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The Joint Plan is intended to reflect the arrangements of the participating organizations and be in harmony with their specific emergency plans and procedures and in accordance with their respective statutes, mandates and obligations. The Joint Plan neither prejudices nor replaces any emergency preparedness and response arrangements of participating organizations (or States), nor does it prejudice the respective roles and responsibilities of the participating organizations as they may be specified by relevant instruments of the respective organizations. However, other international organizations (and States) are encouraged to consider this interagency framework in the context of their own emergency management plans, where applicable.
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Artikel in diesem Heft
- Frontmatter
- Best estimate approach for the evaluation of critical heat flux phenomenon in the boiling water reactors
- Coupled neutronic core and subchannel analysis of nanofluids in VVER-1000 type reactor
- PCTRAN enhancement for large break loss of coolant accident concurrent with loss of offsite power in VVER-1000 simulation
- Experimental study of natural circulation flow instability in rectangular channels
- Exerimental method and preliminary studies of the passive containment water film evaporation mass transfer
- Automated generation of burnup chain for reactor analysis applications
- Fission source sampling in coupled Monte Carlo simulations
- Hysteresis phenomenon in nuclear reactor dynamics
- Investigation of neutronic and safety parameters variation in 5 MW research reactor due to U3O8Al fuel conversion to ThO2 + U3O8Al
- Implementation of meso-scale radioactive dispersion model for GPU
- Solution of the multilayer multigroup neutron diffusion equation in cartesian geometry by fictitious borders power method
- Half-space albedo problem with modified FN method for linear and quadratic anisotropic scattering
Artikel in diesem Heft
- Frontmatter
- Best estimate approach for the evaluation of critical heat flux phenomenon in the boiling water reactors
- Coupled neutronic core and subchannel analysis of nanofluids in VVER-1000 type reactor
- PCTRAN enhancement for large break loss of coolant accident concurrent with loss of offsite power in VVER-1000 simulation
- Experimental study of natural circulation flow instability in rectangular channels
- Exerimental method and preliminary studies of the passive containment water film evaporation mass transfer
- Automated generation of burnup chain for reactor analysis applications
- Fission source sampling in coupled Monte Carlo simulations
- Hysteresis phenomenon in nuclear reactor dynamics
- Investigation of neutronic and safety parameters variation in 5 MW research reactor due to U3O8Al fuel conversion to ThO2 + U3O8Al
- Implementation of meso-scale radioactive dispersion model for GPU
- Solution of the multilayer multigroup neutron diffusion equation in cartesian geometry by fictitious borders power method
- Half-space albedo problem with modified FN method for linear and quadratic anisotropic scattering
