Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic–neutronic simulations-Reference-Cited by-同舟云学术

Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic–neutronic simulations

Published:2012-05 Issue: Volume:246 Page:98-106
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ánchel F.,Barrachina T.,Miró R.,Verdú G.,Juanas J.,Macián-Juan R.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference11 articles.

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2. Practical Non-parametric Statistics;Conover,1980

3. Cronin, J.T., Smith, K.S., Ver Planck, D.M., 1995. SIMULATE-3. Advanced three-dimensional two-group reactor analysis code. Studsvik/SOA-95/18.

4. Downar, T., Lee, D., Xu, Y., Kozlowski, T., Staundenmier, J., 2004. PARCSV2. 6 US NRC Core Neutronics Simulator.

5. Knott, D., Forssén, B.H., Edenius, M., 1995. CASMO-4. A fuel assembly burn-up program. Studsvik/SOA-95/2.

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