Formal qualification of the various sources of an uncertainty employed in the level 2 PSA and the underlying issues

Author:

Ahn Kwang-Il,Yang Joon-Eon,Ha Jaejoo

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference31 articles.

1. A formal approach for quantitative treatment of modeling uncertainties in safety analysis;Ahn;Nuclear Technology,1996

2. Ahn, K.I., Jin, Y.H., 1996b. CONPAS 1.0 Code Package User’s Manual. KAERI/TR-651/96, KAERI, Daejeon, Korea.

3. Development of a computer code, CONPAS, for an integrated level 2 PSA;Ahn;Journal of the Korean Nuclear Society,1998

4. A formal procedure for probabilistic quantification of modeling uncertainties employed in phenomenological transient models;Ahn;Nuclear Technology,2000

5. The explicit treatment of model uncertainties in the presence of aleatory and epistemic parameter uncertainties in risk and reliability analysis;Ahn;Journal of the Korean Nuclear Society,2003

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