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          Control Rod Withdrawal and Sodium Natural Circulation Tests Performed during the PHENIX End-of-Life Experiments

          Closed for proposals

          Project Type

          Coordinated Research Project

          Project Code

          I33012

          CRP

          1455

          Approved Date

          9 May 2008

          Status

          Closed

          Start Date

          15 July 2008

          Expected End Date

          14 July 2011

          Completed Date

          1 January 2013

          Description

          The CRP addresses end-of-life experiments to be performed before the final shut-down of the prototype fast breeder power reactor PHENIX. The CRP will improve the participants’ analytical capabilities in the various fields of research and design of sodium cooled fast reactors through data and codes verification and validation.

          Objectives

          To improve the CRP participants analytical capabilities in various fields of research and design of sodium-cooled fast reactors through code verification and validation, with particular emphasis on temperature and power distribution calculations and the analysis of sodium natural circulation phenomena.

          Specific objectives

          Enhanced international team-building and technical cooperation in the area of fast reactors

          Improved understanding of fast reactor neutronics and thermal hydraulics in safety relevant situations

          Improved understanding of the methodology employed to simulate fast reactors (data and computer codes)

          Improved verification and validation status of this methodology and the used numerical codes

          Impact

          The CRP contributed to improve the know-how on the power and reactivity control as well as some natural circulation phenomena occurring in a large sodium-cooled fast reactors, under transient and accident conditions. It was also very successful as far as the further verification, validation and qualification (V&V&Q) of the neutronic, safety and CFD numerical codes used by the CRP participants to assess performances and conduct safety analyses of innovative sodium-cooled fast reactors under development/design in their country.

          Relevance

          The outcomes of the CRP are of great importance for all the Member States with an active programme on fast reactors. As already stated, the CRP greatly contributed to improve the V&V&Q process of the most advanced nuclear codes used for the design and the safety analysis of innovative fast neutron systems under development/design worldwide.

          CRP Publications

          Type

          Paper at International Conference

          Year

          2012

          Description

          Proceedings of ICAPP'12 - Paper 12287: Overall Results of and Lessons Learned from the IAEA CRP on Sodium Natural Circulation Test Performed during the PHENIX End-of-Life Experiments

          Country/Organization

          USA

          Type

          Paper in peer-reviewed international Journal

          Year

          2013

          Description

          Nuclear Engineering and Design 258 (2013) 189-198 - International Benchmark on the Natural Convection Test in PHENIX Reactor

          Country/Organization

          USA

          Type

          TECDOC-1703

          Year

          2013

          Publication URL

          http://www.dgdingfa.net/NuclearPower/Publications/2014/index.html

          Description

          Full reporting of the benchmark analyses on the natural circulation test performed during the PHENIX End-of-Life Experiments

          Country/Organization

          IAEA

          Type

          TECDOC-1742

          Year

          2014

          Publication URL

          http://www.dgdingfa.net/NuclearPower/Publications/2014/index.html

          Description

          Full reporting of the benchmark analyses on the Control Rod Withdrawal Tests performed during the PHENIX End-of-Life Experiments

          Country/Organization

          IAEA

          Type

          Special Session at International Conference

          Year

          2014

          Description

          7 papers from CRP participants and the IAEA presented at a special session of the PHYSOR2014 Conference

          Country/Organization

          JAPAN

          Type

          Paper at International Conference

          Year

          2014

          Description

          PHYSOR2014 - The Role of Reactor Physics Toward a Sustainable Future: IAEA Benchmark Calculations on Control Rod Withdrawal Test Performed During PHENIX End-of-Life Experiments Benchmark Results and Comparison

          Country/Organization

          JAPAN

          Type

          Paper at International Conference

          Year

          2013

          Description

          Proceedings of ICAPP'13 - Paper FA081 - Benchmark Calculations on Control Rod Withdrawal Tests Performed during PHENIX End-of-Life Experiments

          Country/Organization

          USA

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