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Keywords: source term
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Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A044, August 4–5, 2020
Paper No: ICONE2020-16562
... aerosol release, the Source Term (ST), based on aerosol transport from a fire room to a corridor and from the corridor to the environment. However, no existing literature has been found on estimating ST from this multi-room facility configuration. This paper contributes the following to aerosol transport...
Topics: Aerosols, Fire
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A045, August 4–5, 2020
Paper No: ICONE2020-16584
... Abstract The work presented in this paper applies the MELCOR code developed at Sandia National Laboratories to evaluate the source terms from potential accidents in non-reactor nuclear facilities. The present approach provides an integrated source term approach that would be well-suited...
Proceedings Papers

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A045, July 29–August 2, 2013
Paper No: ICONE21-16526
... Fukushima Daiichi evacuation health effects TID-14844 source term safety goals In nuclear safety, the source term is introduced to provide adequate isolation of the nuclear hazards from the public, by establishing a concept of ‘effective distance.’ This combines a geographical...
Proceedings Papers

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 351-359, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54258
... in this paper, the iodine source term has been evaluated for two-loop PWR under severe accident initiated due to LOCA. The TMI-2 reactor is considered as the reference reactor. The modeling and simulations are carried out by developing a MATLAB base program that uses the post-accident conditions and core...
Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 457-462, May 17–21, 2010
Paper No: ICONE18-29326
... spring-plenum region of the LWR fuel. If successful this innovation can be implemented in existing and next generation LWRs and may: • reduce accident source term (releasable FPGs); • enhance reactor safety and acceptance; • extend fuel life suppressing clad swelling and fuel failure; • reduce thermal...
Proceedings Papers

Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 549-556, May 11–15, 2008
Paper No: ICONE16-48044
..., thermal hydraulic response inside the containment compartments, release and accumulation of H2 and fission product (FP) source terms, their leakage into environment were simulated and investigated. The effectiveness of preventive and mitigative measures, such as dedicated core depressurization system...
Proceedings Papers

Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 721-726, May 11–15, 2008
Paper No: ICONE16-48692
... into volatile iodine thus influencing the iodine source term. Even low conversion rates might lead to a significant influence on the concentration of gaseous iodine in the early phase of an accident where high CsI/I 2 ratios of 100:1 or even higher can be expected. In the frame of the German national THAI...