Neutronics Benchmark of CEFR Start-Up Tests
Closed for Proposals
Project Type
Coordinated Research ProjectProject Code
I31032
CRP
2173
Approved Date
20/12/2017Project Status
ClosedStart Date
07/04/2018Expected End Date
31/12/2024Completed Date
06/02/2026Participating Countries
Belgium, Switzerland, China, Germany, Finland, France, United Kingdom of Great Britain and Northern Ireland, Hungary, India, Italy, Japan, Republic of Korea, Mexico, Romania, Russian Federation, Slovakia, Ukraine, United States of AmericaDescription
The title update proposed by expert at CM:Neutronics Benchmark of CEFR Start-Up Tests The Coordinated Research Project (CRP) will focus on neutronics benchmark analysis of the physics start-up tests performed at the China Experimental Fast Reactor (CEFR) in 2010-2011. CEFR is a small-size sodium cooled fast reactor with a high neutron leakage core fuelled with uranium oxide and stainless-steel radial reflector. Benchmark analysis of CEFR physics start-up tests will include evaluation of the criticality, control rod worth, reactivity effects, and neutron spectral characteristics. The recorded experimental data from the CEFR start-up will provide an excellent opportunity for validation of the physical models and neutronics simulation codes.
Objectives
The overall objective of the CRP is to improve the Member States' analytical capabilities in the field of fast reactor simulation and design by international validation and qualification of codes currently employed in the field of fast reactor neutronics through benchmark study based on experimental data obtained by CIAE in 2010-2011 during the CEFR start-up tests. The CRP will be implemented as a programmatic activity of the IAEA Project 1.1.5.3 “Advanced technologies for fast and gas cooled reactors” starting with the IAEA Program and Budget Cycle 2018 – 2019. The Project 1.1.5.3 has the objective, among others, to enable Member States to make informed decisions on the development of new or advanced fast reactor designs and to increase cooperation between Member States in achieving advances in fast reactor technology development through international collaborative R&D. Given its aforementioned overall objective, the CRP clearly responds to the objectives of the IAEA Project 1.1.5.3.
Specific Objectives
Collect, evaluate and share experimental data obtained by CIAE during CEFR start-up tests.
Perform benchmark analysis by simulation of specific CEFR Physics Start-up tests using different codes, methods and models by the participating institutions and jointly analyse the results of calculations.
Jointly develop a benchmark specification, including Detailed input data on: reactor core axial and radial layout, including positions of the control rods; detailed description of fuel and control rod assemblies; isotopic composition of core materials; CEFR start-up tests description; experimental data measured in physics start-up tests (values, locations, uncertainties). Simulation results and experimental data to be compared: effective multiplication factor; control rod worth; reactivity effects; neutron spectral characteristics.
Calculation of correction factor between homogeneous and heterogeneous models (optional).
Publish a benchmark report as an IAEA technical publication.
Analysis of uncertainties (optional).
Collect, evaluate and share experimental data obtained by CIAE during CEFR start-up tests.
Perform benchmark analysis by simulation of specific CEFR Physics Start-up tests using different codes, methods and models by the participating institutions and jointly analyse the results of calculations.
Jointly develop a benchmark specification, including Detailed input data on: reactor core axial and radial layout, including positions of the control rods; detailed description of fuel and control rod assemblies; isotopic composition of core materials; CEFR start-up tests description; experimental data measured in physics start-up tests (values, locations, uncertainties). Simulation results and experimental data to be compared: effective multiplication factor; control rod worth; reactivity effects; neutron spectral characteristics.
Calculation of correction factor between homogeneous and heterogeneous models (optional).
Publish a benchmark report as an IAEA technical publication.
Analysis of uncertainties (optional).
Impact
The CRP consists of eight work packages. Six work packages include six measurements of criticality per fuel loading, control rod worth, sodium void reactivity, temperature reactivity, subassembly swap reactivity, and foil activation measurement. The remaining work packages consist of two numerical benchmarks, which include the evaluation of integral reactivity coefficients and analyses of sensitivity and uncertainty propagation. Even though the integral reactivity coefficients and uncertainties propagation have not been measured in the start-up tests, participants agreed on the numerical benchmarks to understand the integral safety feature of the CEFR.
About 30 international organizations from 18 member countries and international organizations participated in the CRP using a broad spectrum of computation tools and neutron libraries. Computation tools can be divided into two groups: deterministic and stochastic. The deterministic codes include legacy codes (DIF3D, ERANOS, etc.) and newly developing codes (NAS, etc.) based on multiple diffusion and transport approximations. The stochastic codes include MCNP, SERPENT, MVP, etc. The neutron libraries are also generated from various evaluated nuclear data, such as ENDF/B (mostly version VII and VIII), JEFF, JENDL, etc. Thus, participants had additional opportunities to compare the performance of computation codes and neutron libraries through this CRP.
Relevance
Relevant to IAEA project 1000154 and Member States perusing fast reactor technology deployment, software development (validation) and licensing of these types of reactors.
CRP Publications
IAEA
PHYSOR2020 Confrence
2020
MONTE CARLO SIMULATION OF NEUTRONICS START-UP TESTS AT CHINA EXPERIMENTAL FAST REACTOR (CEFR)
UNIST, South Korea
Annals of Nuclear Energy
2020
Neutronic simulation of the CEFR experiments with the nodal diffusion code system RAST-F
IAEA
FR22 Conference
2022
International Conference on Fast Reactors and Related Fuel Cycles FR22: Sustainable Clean Energy for the Future