Search for dissertations about: "Nuclear best estimate codes"

Showing result 1 - 5 of 6 swedish dissertations containing the words Nuclear best estimate codes.

2. 1. Nuclear data uncertainty quantification and data assimilation for a lead-cooled fast reactor : Using integral experiments for improved accuracy

   Author : Erwin Alhassan; Henrik Sjöstrand; Rochman Dimitri; Michael Österlund; Stephan Pomp; Oscar Cabellos; Uppsala universitet; []
   Keywords : NATURVETENSKAP; NATURAL SCIENCES; Total Monte Carlo; ELECTRA; nuclear data; uncertainty propagation; integral experiments; nuclear data adjustment; uncertainty reduction;

   Abstract : For the successful deployment of advanced nuclear systems and optimization of current reactor designs, high quality nuclear data are required. Before nuclear data can be used in applications they must first be evaluated, tested and validated against a set of integral experiments, and then converted into formats usable for applications. READ MORE

4. 2. Uncertainty and sensitivity analysis applied to LWR neutronic and thermal-hydraulic calculations

   Author : Augusto Hernandéz Solís; Chalmers tekniska högskola; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; sensitivity analysis; Nuclear best estimate codes; uncertainty analysis;

   Abstract : The deterministic modeling of LWRs begins with the computation of energy‐collapsed and homogenizedmacroscopic cross‐sections by means of a lattice code. Once these parameters are functionalized as a functionof the reactor state variables and discretized in space, they are used as input variables by core simulators inorder to calculate the spatial distribution of the neutron flux and thus, the spatial distribution of the power. READ MORE

5. 3. Uncertainty and Sensitivity Analysis Applied to the Validation of BWR Bundle Thermal-Hydraulic Calculations

   Author : Augusto Hernandéz Solís; Chalmers tekniska högskola; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Latin Hypercube sampling; uncertainty and sensitivity analysis; Thermal‐hydraulic codes; simple random sampling; reactor safety analysis; BFBT benchmark;

   Abstract : In recent years, more realistic safety analyses of nuclear reactors have been based on best estimate (BE) computercodes. The need to validate and refine BE codes that are used in the predictions of relevant reactor safetyparameters, led to the organization of international benchmarks based on high quality experimental data. READ MORE

6. 4. Informing Severe Accident Management Guidelines for a Pressurized Water Reactor with MELCOR Simulations

   Author : Nan Zhao; Sevostian Bechta; Jinho Song; KTH; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Severe accident management guidelines SAMG ; SAMG verification validation; numerical simulation; SAMG entry condition; SAMG actions; primary-side bleed feed.; Kärnenergiteknik; Nuclear Engineering;

   Abstract : Severe accident management guidelines (SAMGs) play an important role in the hierarchical structure of the defense-in-depth (DiD) principle of reactor safety. Among different methods to verify and validate the effectiveness of SAMG on mitigating severe accident consequences, the approach of numerical simulations using best-estimate computer codes was extensively applied to evaluate the SAMG and SAM actions. READ MORE

7. 5. Sensitivity and Uncertainty Analysis of BWR Stability

   Author : Ivan Gajev; Tomas Lefvert; Paolo Vinai; KTH; []
   Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; BWR Stability; Sensitivity; Uncertainty; Engineering physics; Teknisk fysik; SRA - Energy; SRA - Energi;

   Abstract : Best Estimate codes are used for licensing, but with conservative assumptions. It is claimed that the uncertainties are covered by the conservatism of the calculation. READ MORE