Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat

Abstract The decay heat rate of five spent nuclear fuel assemblies of the pressurized water reactor type were measured by calorimetry at the interim storage for spent nuclear fuel in Sweden. Calculations of the decay heat rate of the five assemblies were performed by 20 organizations using different codes and nuclear data libraries resulting in 31 results for each assembly, spanning most of the current state-of-the-art practice. The calculations were based on a selected subset of information, such as reactor operating history and fuel assembly properties. The relative difference between the measured and average calculated decay heat rate ranged from 0.6% to 3.3% for the five assemblies. The standard deviation of these relative differences ranged from 1.9% to 2.4%.

[1]  C. J. Díez,et al.  The joint evaluated fission and fusion nuclear data library, JEFF-3.3 , 2020, The European Physical Journal A.

[2]  G. Parks,et al.  Neutron clustering as a driver of Monte Carlo burn-up instability , 2020, Annals of Nuclear Energy.

[3]  P. Jansson,et al.  Data from calorimetric decay heat measurements of five used PWR 17x17 nuclear fuel assemblies , 2019, Data in brief.

[4]  J. Leppänen,et al.  New energy deposition treatment in the Serpent 2 Monte Carlo transport code , 2019, Annals of Nuclear Energy.

[5]  F. Brown Doppler Broadening Resonance Correction for Free-gas Scattering in MCNP6.2 , 2019 .

[6]  R. A. Forster,et al.  MCNP Version 6.2 Release Notes , 2018 .

[7]  R. Q. Wright,et al.  ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data , 2018 .

[8]  Bradley T Rearden,et al.  SCALE Code System , 2016 .

[9]  F. Álvarez-Velarde,et al.  Validation of the burn-up code EVOLCODE 2.0 with PWR experimental data and with a Sensitivity/Uncertainty analysis , 2014 .

[10]  C. Calvin,et al.  OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development , 2014, ICS 2014.

[11]  Tuomas Viitanen,et al.  The Serpent Monte Carlo Code: Status, Development and Applications in 2013 , 2014, ICS 2014.

[12]  P. Bourdot,et al.  Experimental Validation of the DARWIN2.3 Package for Fuel Cycle Applications , 2013 .

[13]  Ian C Gauld,et al.  Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE , 2012 .

[14]  G. V. D. Eynde,et al.  Advanced Method for Calculations of Core Burn-Up, Activation of Structural Materials, and Spallation Products Accumulation in Accelerator-Driven Systems , 2012 .

[15]  N. M. Larson,et al.  ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data , 2011 .

[16]  K. Shibata,et al.  JENDL-4.0: A New Library for Nuclear Science and Engineering , 2011 .

[17]  Alain Hébert,et al.  Development of the Subgroup Projection Method for Resonance Self-Shielding Calculations , 2009 .

[18]  I. Gauld,et al.  LWR Cross Section Libraries for ORIGEN-ARP in SCALE 5.1 , 2006 .

[19]  日本原子力研究所,et al.  MVP/GMVP II : General purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods , 2005 .

[20]  C. Garzenne,et al.  DARWIN: An Evolution Code System for a Large Range of Applications , 2000 .

[21]  D. W. Muir,et al.  Recent development of the CINDER`90 transmutation code and data library for actinide transmutation studies , 1995 .

[22]  A. G. Croff,et al.  User's manual for the ORIGEN2 computer code , 1980 .

[23]  Samaneh Rakhshan Pouri,et al.  PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems , 2018 .

[24]  C. Wemple,et al.  Update and evaluation of decay data for spent nuclear fuel analyses , 2017 .

[25]  P. Blaise,et al.  APOLLO2.8 : A VALIDATED CODE PACKAGE FOR PWR NEUTRONICS CALCULATIONS , 2009 .

[26]  K. Smitha,et al.  CASMO-5 energy release per fission model , 2008 .

[27]  S. Langenbuch,et al.  LWR decay heat calculations using a GRS improved ENDF/B-VI based ORIGEN data library , 2007 .

[28]  J. E. Gindler,et al.  CRITICAL REVIEW OF THE ENERGY RELEASED IN NUCLEAR FISSION. , 1971 .