Uncertainty analysis of containment dose rate for core damage assessment in nuclear power plants
활용도 Analysis
논문 Analysis
연구자 Analysis
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Uncertainty analysis of containment dose rate for core damage assessment in nuclear power plants' 의 참고문헌
XSOR Codes User's Manual, NUREG/ CRd5360
Westinghouse Owners Group Post Accident Core Damage Assessment Methodology
Westinghouse Owners Group Core Damage Assessment Guidance
Utilisation of the SESAME system for diagnosis and prognosis of plant status during an emergency in a French PWR
Using Bayesian Belief Network (BBN) Modelling for Rapid Source Term Prediction e Final Report, NKS-293
The generalization of Latin hypercube sampling
The Mesorad Dose Assessment Model, NUREG/CR-4000
Tables of X-Ray Mass Attenuation Coefficients and Mass Energy-absorption Coefficients from 1 KeV to 20 MeV for Elements Z = 1 to 92 and 48 Additional Substances of Dosimetric Interest
State-of-the-Art Reactor Consequence Analyses Project
Source Term Estimation during Incident Response to Severe Nuclear Power Plant Accidents, NUREG 1228
Severe Accident Risks: an Assessment for Five U.S. Nuclear Power Plants, NUREG-1150
SAMEX: a severe accident management support expert
Research and application of SESAME system
Reactor Safety Study: an Assessment Accident Risks in U.S. Commercial Nuclear Power Plants, WASH-1400 (NUREG/CR-0400)
RTM-96 (NUREG/BR-0150). Response Technical Manual, vol. 1
RASCAL 3.0.5: Description of Models and Methods, NUREG-1887
RASCAL 3.0.5: Description of Models and Methods, NUREG-1887
Possibilities T. Consequences of Major Accidents in Large Nuclear Power Plants, WASH 740
PWR containment radiation levels calculation related to core conditions
Multilevel Monte Carlo and Improved Timestepping Methods in Atmospheric Dispersion Modelling
Modifications Proposed by the Westinghouse Owners Group to the Core Damage Assessment Guidelines and Post Accident Sampling System Requirements
MCNPea General Monte Carlo Neparticle Transport Code
Generic Models and Parameters for Assessing the Environment Transfer of Radionuclides from Routine Releases
Generic Assessment Procedures for Determining Protective Actions during a Reactor Accident, IAEA-TECDOC-955
Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor
Development of rapid atmospheric source term estimation system for AP1000 nuclear power plant
Development of a risk-informed diagnostics and prognostics system to support severe accident management
Clarification of TMI Action Plan Requirements, NUREG-0737
CFD/Monte-Carlo neutron transport coupling scheme, application to TRIGA reactor
An assessment of effectiveness of core exit temperatures with respect to PWR core damage state using RELAP/SCDAPSIM/MOD3.4
An R-squared measure of goodness of fit for some common nonlinear regression models
Accident Source Terms for Light-water Nuclear Power Plants, NUREG-1465
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Uncertainty analysis of containment dose rate for core damage assessment in nuclear power plants'
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