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          Benchmark Analysis of an EBR-II Shutdown Heat Removal Test

          Closed for Proposals

          Project Type

          Coordinated Research Project

          Project Code

          I31021

          CRP

          1830

          Approved Date

          27 February 2012

          Project Status

          Active - Ongoing

          Start Date

          23 May 2012

          Expected End Date

          23 May 2016

          Completed Date

          30 May 2016

          Description

          The Coordinated Research Project (CRP) addresses Shutdown Heat Removal Tests (SHRT) performed at the Experimental Breeder Reactor-II (EBR-II) within the framework of the US Integral Fast Reactor (IFR) development and demonstration program. The CRP's will improve the participants’ simulation capabilities in the various fields of research and design of sodium cooled fast reactors through data and codes validation and qualification. The CRP work plan includes for each of the participants (i) EBR-II model development on the basis of the specifications provided by ANL for selected shutdown heat removal test(s); (ii) test simulations; (iii) compilation of results; (iv) comparisons of results against test data and against the other participants; and (v) analysis and recommendations for improved modelling aiming at the uncertainties reduction.

          Objectives

          To improve the Member States' analytical capabilities in the field of fast reactor simulation and design contributing towards extending the validation and verification of state-of-the-art liquid metal cooled fast reactor codes to accurately simulate the primary coolant loop behaviour during loss-of-flow accidents; particularly on predicting natural convective cooling accurately.

          Specific Objectives

          Evaluation of the following parameters that predict the transient behaviour of the primary coolant loop:
          - Reactor core flow and temperatures (measurements obtained from the instrumented subassemblies XX09 and XX10 for axial distributions at fuel centerline, fuel surface, coolant, and structures);
          - IHX sodium outlet temperature
          - Reactor inlet sodium temperature and flow rate

          Evaluation of uncertainties for prediction of:
          - Flow rates;
          - Fuel, cladding, coolant, and structure temperatures along the length of a subassembly;
          - Transition to natural circulation.

          Simulation of shutdown heat removal tests using different codes, data, and models

          Contact CRP Officer

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