Hiroshima and Nagasaki Verification of an Unstructured Mesh-Based Transmutation Toolkit

Abstract In order to model the activated isotopes and resulting dose from a nuclear detonation in an urban environment, the Activation and Transmutation of Isotopes in an Unstructured Mesh (ACTIUM) Python toolkit has been developed to combine the unstructured mesh–based particle transport capability of MCNP6.2 with the CINDER2008 transmutation code to produce quantities of interest for the post-detonation nuclear forensics and weapons effects communities. The ACTIUM toolkit has been implemented and validated with a number of test cases from a simple analytic model to a case study of the urban detonation in Nagasaki, Japan. The ACTIUM approach is the first of its kind to couple the latest release of CINDER2008 as a part of the Activation in Accelerator Radiation Environments (AARE) package with MCNP6.2 and produce transmuted quantities per time step on an unstructured mesh for the nuclear forensics and weapon effects communities. ACTIUM uses the latest ENDF/B-VIII.0, TENDL2017, and JENDL4 cross-section libraries for the transmutation calculations and includes methods for producing material cards for the initial MCNP6.2 unstructured mesh calculation based on highly detailed materials often found in urban environments on a city-specific basis.

[1]  Richard L. Holmes,et al.  Output of Fat Man and Little Boy Devices , 2013 .

[2]  P. V. Subhash,et al.  ACTYS-ASG, tool for coupling ACTYS-1-GO with ATTILA , 2018 .

[3]  H. Hall,et al.  Preliminary investigation for the development of surrogate debris from nuclear detonations in marine-urban environments , 2017, Journal of Radioanalytical and Nuclear Chemistry.

[4]  Paul P. H. Wilson,et al.  Shutdown dose rate analysis with CAD geometry, Cartesian/tetrahedral mesh, and advanced variance reduction , 2016 .

[5]  M J Kristo,et al.  The state of nuclear forensics , 2013 .

[6]  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 .

[7]  B. Colling,et al.  Comparative Study of Neutronics Analysis Techniques for Radioactive Waste Assessment , 2018, Fusion Science and Technology.

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

[9]  Cheol-Woo Lee,et al.  Shutdown dose rate analysis with unstructured tetrahedral element based R2S method using deterministic transport solver AETIUS , 2018, Fusion Engineering and Design.

[10]  J McGahan,et al.  Radiation Dose Reconstruction U.S. Occupation Forces in Hiroshima and Nagasaki, Japan, 1945-1946. , 1980 .

[11]  Activation analysis study on Li-ion batteries for nuclear forensic applications , 2015 .

[12]  Arkady Serikov,et al.  Verification and validation of the R2Smesh approach for the calculation of high resolution shutdown dose rate distributions , 2012 .

[13]  Arjan J. Koning,et al.  Modern Nuclear Data Evaluation with the TALYS Code System , 2012 .

[14]  H. Hall,et al.  Review of current nuclear fallout codes. , 2017, Journal of environmental radioactivity.

[15]  Joel A. Kulesza,et al.  A Python Script to Convert MCNP Unstructured Mesh Elemental Edit Output Files to XML-based VTK Files , 2019 .

[16]  Hideo Joho,et al.  Deliverable type: Contributing WP: , 2022 .

[17]  Rosaria Villari,et al.  Shutdown dose rate benchmark experiment at JET to validate the three-dimensional Advanced-D1S method , 2012 .

[18]  Robert Boone Gilbreath,et al.  Development of Nuclear UnderGround Engineered Test Surrogates for Technical Nuclear Forensics Exploitation , 2017 .

[19]  Elizabeth Keegan,et al.  Nuclear Forensics: Scientific Analysis Supporting Law Enforcement and Nuclear Security Investigations. , 2016, Analytical chemistry.

[20]  K. Holbert,et al.  Li-Ion Batteries Used as Ubiquitous Neutron Sensors for Nuclear Forensics , 2013, IEEE Transactions on Nuclear Science.

[21]  Felix Warmer,et al.  Verification of different Monte Carlo approaches for the neutronic analysis of a stellarator , 2017 .

[22]  Ulrich Fischer,et al.  Rigorous mcnp based shutdown dose rate calculations: computational scheme, verification calculations and application to ITER , 2002 .

[23]  A. Turner,et al.  MCR2S Unstructured Mesh Capabilities for use in Shutdown Dose Rate Analysis , 2015 .