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At least 1,567 records · Page 87

Use of Data Libraries for IAEA Nuclear Security Assessment Methodologies (NUSAM) [section 5.4]

Data libraries are essential for the characterization of the facility and provide the documented input which enables the facility assessment results and subsequent conclusions. Data Libraries are historical, verifiable, quantified, and applicable collections of testing data on different types of barriers, sensors, cameras, procedures, and/or personnel. Data libraries are developed and maintained as part of any assessment program or process. Data is collected during the initial stages of facility characterization to aid in the model and/or simulation development process. Data library values may also be developed through the use of state testing centers and/or site resources by testing different types of barriers, sensors, cameras, procedures, and/or personnel. If no data exists, subject matter expert opinion and manufacturer's specifications/ testing values can be the basis for initially assigning values, but are generally less reliable and lack appropriate confidence measures. The use of existing data libraries that have been developed by a state testing organization reduces the assessment costs by establishing standard delay, detection and assessment values for use by multiple sites or facilities where common barriers and alarms systems exist.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Study of Applications of Radiological Data Fusion for Nuclear Security and Non-proliferation Applications

This report describes the radiological Scene Data Fusion (SDF) technology and the potential to apply the SDF technology to a variety of problems related to nuclear non-proliferation, radiological security, and other missions related to the national nuclear security agency and the US government, more broadly. The application space was conceived by both the authors of this report and the many scientists and stakeholders they interviewed. In order to successfully apply the SDF technology to the various applications, further research and development is often necessary and those R&D steps are also outlined herein.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

ENDF/B-VIII.1: Alpha Reaction Sublibrary

The alphas sublibrary aims to describe nuclear reactions between incident alpha particles and different nuclei. For ENDF/B-VIII.1, the LLNL ECPL evaluation for 6Li, and the JENDL-based NNL evaluations of 9 Be and 16,17 O were adopted. Also, there were minor fixes done to 4 He.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Decay Reaction Sublibrary

The decay sublibrary aims to describe all known spontaneous decays and branching ratios for all nuclei across the nuclide chart. ENDF/B-VIII.1 remains unchanged from ENDF/B-VIII.0 for the decay sublibrary.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Deuteron Reaction Sublibrary

The deuterons sublibrary aims to describe nuclear reactions between incident deuteron particles and different nuclei. For ENDF/B-VIII.1, we adopted additions and corrections to the ENDF/B-VIII.0 d+t file, as well as new LANL evaluation updates for 3 He and 6 Li.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Helium-3 Reaction Sublibrary

The Helium-3 (Helions) sublibrary aims to describe nuclear reactions between incident 3 He particles and different nuclei. For ENDF/B-VIII.1, we adopted a new 4He evaluation from the INDEN collaboration and the LLNL ECPL evaluation for 7 Li.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Neutron Reaction Sublibrary

The neutrons sublibrary aims to describe nuclear reactions between incident neutron particles and different nuclei. For ENDF/B-VIII.1, many neutron files were re-evaluated or received major changes. A new 239Pu evaluation was jointly-produced by IAEA, LANL, LLNL and ORNL bringing important updates to fission neutron multiplicity, Prompt Fission Neutron Spectrum, resonance and fast regions. Around one third of the new neutron evaluations were performed as part of the INDEN collaboration, including 16,18 O, 19 F, 28,29,30 Si, 63,65 Cu, 50,51,52,53,54 Cr, 55 Mn, 54,56,57 Fe, 139 La, 233,235,238 U, 240,241 Pu. Important non-INDEN evaluations include 234,236 U, 206,207,208 Pb, 181 Ta, 88 Sr, 140,142 Ce, Pt and Dy isotopes, and many others. Also, dosimetry reactions from IRDFF-II were adopted for many materials.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Neutron Induced Fission Product Yields Sublibrary

The neutron-induced fission yields (NFY) sublibray aims to describe fission yields in neutron-induced reactions. For ENDF/B-VIII.1, there were no new fission yields complete evaluations. However, an important fix the 241 Pu NFY file was implemented, solving a long-standing anomalous discontinuity issue accidentally introduced in ENDF/B-VI.2, decades ago. Additionally, many erroneously large uncertainties, present in NFY from ENDF/B-VIII.0, were corrected.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Proton Reaction Sublibrary

The protons sublibrary aims to describe nuclear reactions between incident proton particles and different nuclei. For ENDF/B-VIII.1, compared to ENDF/B-VIII.0, there were only evaluation updates for 4 He.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Spontaneous Fission Product Yields Reaction Sublibrary

The spontaneous fission yields (SFY) sublibray aims to describe fission yields that happen spontaneous, without any incident particle. For ENDF/B-VIII.1, there were no new fission yields complete evaluations. However, many erroneously large uncertainties, present in both SFY from ENDF/B-VIII.0, were corrected.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Neutron Standards Sublibrary

The neutron standards sublibrary describes specific reaction cross sections, in a limited range, that are so well-known that they are used as ratios or references in other measurements. ENDF/B-VIII.1 remains unchanged from ENDF/B-VIII.0 for the neutron standards sublibrary

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Thermal Neutron Scattering Sublibrary

The thermal neutron scattering law (TSL) sublibrary aims to describe the interaction of incident neutrons at thermal or sub-thermal energies with different compound materials such fuels, moderators and special-purpose materials. In ENDF/B-VIII.1 there was a large number of new and updated TSL evaluations, including traditional moderators (light water, Beryllium metal, Beryllium Oxide, Calcium Hydride, plastics (Polystyrene and Lucite), graphite (reactor-grade and crystalline), anhydrous Hydrogen Fluoride, and heavy paraffinic oil); exotic moderators (Beryllium Carbide, Zirconium Hydride, Yttrium Hydride, Lithium-7 Hydride and Deuteride), FLiBe molten salt, structural materials and cladding (Silicon Carbide, Silicon Dioxide, Zirconium Carbide), fuels (Plutonium Dioxide, Uranium Carbide, Uranium metal, Uranium Nitride, Uranium Dioxide, Uranium Hydride), and special purpose materials. In ENDF/B-VIII.1 we also distribute alongside the evaluated files, a comma-separated file (CSV), named TSL_MAT_numbers.csv, which lists all evaluated files in the current release and their corresponding unique MAT number.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ENDF/B-VIII.1: Triton Reaction Sublibrary

The tritons sublibrary aims to describe nuclear reactions between incident triton particles and different nuclei. For ENDF/B-VIII.1, compared to ENDF/B-VIII.0, there were only evaluation updates for 4 He.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Consolidating Data on Spent Nuclear Fuel into a Unified Database

This paper describes the comprehensive commercial spent nuclear fuel (SNF) database, the Unified Database (UDB), and discusses the UDB's (1) content and design with limited data examples and potential applications, (2) external interfaces, and (3) planned enhancements to streamline national SNF data collection and preservation. The UDB is the nucleus of the Used Nuclear Fuel Storage, Transportation and Disposal Analysis Resource and Data System (UNF-ST and DARDS). The UDB is being developed for the US Department of Energy Office of Nuclear Energy (DOE-NE) to provide a credible, controlled data source for key information for: various analytical purposes, including assessing issues and uncertainties related to the extended storage and transportability of SNF after extended storage; supporting research and development (R and D) prioritization; and preserving SNF related information for future generations. The UDB will serve as a national resource for use by DOE-NE or a future management and disposal organization in planning for future storage, transport, and disposal of SNF. The UDB is also being designed with the flexibility to provide information on greater-than-class C (GTCC) waste, government-owned SNF, and high-level radioactive waste (HLW). (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Results of the Collaborative International Evaluated Library Organization (CIELO) Project

Simulation of nuclear systems requires complete data that represents the relevant nuclear physics. This requires many types of experimental measurements, theoretical physics, semi-empirical models and software systems, as well as experts to integrate and guide the process. This discipline is collectively known as nuclear data, and separate programmes within various European countries, the USA, Japan, Russia, and other OECD Nuclear Energy Agency (NEA) member countries have been operating for many decades. The NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC) exists to improve the quality and completeness of nuclear data by bringing together representatives of the major nuclear data evaluation projects of NEA member countries and selected Invitees. The Sub- and Expert Groups of the WPEC typically focus on specific technical topics, while the Collaborative International Evaluated Library Organisation Pilot Project (CIELO) was established to generate complete evaluations for a selection of the most important isotopes for criticality in nuclear technologies: 235,238 U, 239 Pu, 56 Fe, 16 O and 1 H.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

ORNL Neutron Cross-Section Measurements in the Resolved Resonance Range for the NCSP

Nuclear criticality simulations test the quality and the consistency of the existing nuclear evaluated data libraries such as ENDF/B, JEFF, or JENDL. In some cases, the cross-section evaluations of those libraries are found insufficient to describe accurately criticality benchmarks. The US Nuclear Criticality Safety Program (NCSP) collaborates with the Joint Research Center (JRC) in Geel, Belgium, to perform high-resolution neutron-induced cross section measurements at the Geel Linear Accelerator (GELINA) to resolve deficiencies in nuclear data that have been emerging in criticality calculations. Problems with nuclear data include insufficient neutron energy range, missing covariances, and problems with previous experiments. For example, the use of the ENDF/B-VII.1 neutron cross section data for vanadium, cerium and zirconium in nuclear criticality safety calculations shows discrepancies between benchmark calculations measurements and demonstrates the need for reliable covariance data. For new covariances of existing data, a reevaluation of the old cross section data is needed. However, these data are in many cases no longer available. This deficit can be overcome only by obtaining new experimental data to serve as the basis of a new evaluation. Recent measurements were made of the neutron total and capture cross sections of natural vanadium and natural zirconium in the neutron energy range from 100 eV to several hundred keV. These measured data will be used to improve representation of the cross sections since most of the available evaluated data rely on old measurements.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗