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Banerjee, Kaushik

Publications and source records attributed to Banerjee, Kaushik.

50 records · Page 3
All sourcesNASA NTRSDOE OSTI
DOE OSTI2019

Demonstration and Feasibility Analyses of Using the Dual-Purpose Canister Drain Pipe to Support the Filling Process

This work documents experiments that are being used to determine the feasibility of filling dual-purpose canisters (DPCs) using the existing drain pipe. Mercury was identified as a surrogate filler for the initial experiments. Oak Ridge National Laboratory’s Target Test Facility (TTF), which is a full-scale Spallation Neutron Source (SNS) prototypical mercury loop, is being used for the planned pipe experiments using mercury. The pipe experiments were divided into two phases to provide a separate effects approach to the problem and to allow for development of system scalability. The first phase included taking strain measurements in a short length pipe, as well as measurements of flow-induced vibration. The second phase consists of the design and construction of a separated mercury flow loop capable of hosting exchangeable test sections and more localized instrumentation. Data acquisition of Phase I was performed during this work and is presented in the form of strain measurements and vibration frequency.

Dominguez-Ontiveros, Elvis↗
DOE OSTI2019

The MAVRIC-Shift Sequence in SCALE for Radiation Transport and Shielding Calculations with Automated Variance Reduction and Parallel Computing

A new MAVRIC-Shift sequence has been implemented and tested within the SCALE Code System to provide parallel computing capabilities for radiation transport and shielding analysis with automated variance reduction. This new sequence provides the most widely used capabilities of the MAVRIC sequence and also features the highly scalable Shift Monte Carlo solver, thus enabling faster time-to-solution when run on multiple cores. This report provides a summary of the theory of variance reduction approaches in MAVRIC and the integration of Shift into the MAVRIC sequence of SCALE. Similarities and differences in methodologies between the traditional MAVRIC sequence and the new MAVRIC-Shift sequence are discussed. Validation cases are presented with models of radiation shielding experiments and verification is provided with a series of practical application cases of interest to the US Nuclear Regulatory Commission, the sponsors of this work, including spent nuclear fuel transportation and storage systems.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2019

Initial Neutronics and Thermal-Hydraulic Coupling for Spent Nuclear Fuel Canister

This report documents work performed supporting the US Department of Energy (DOE) Nuclear Energy Spent Fuel and Waste Disposition, Spent Fuel and Waste Science and Technology, under work breakdown structure element 1.08.01.03.05, “Direct Disposal of Dual Purpose Canisters.” In particular, this appendix fulfills the M3 milestone, M3SF-19OR010305015, “Multiphysics criticality consequence analysis capability development status report,” as Revision 1 to M3SF-19OR010305016, “Initial neutronic and thermal hydraulic coupling for waste package” within work package SF-19OR01030501, “Direct Disposal of Dual Purpose Canisters–ORNL.” This report presents the initial development status of a multiphysics criticality consequence simulation framework, Terrenus. Terrenus currently couples two physics codes: the Monte Carlo radiation transport code Shift and the thermal-hydraulics code COBRA-SFS. The coupling capability has been demonstrated using a simplified 3 x 3 fuel pin lattice. Terrenus will be developed further to include (1) general geometry package support, allowing modeling of a spent nuclear fuel (SNF) cask with all structural details, (2) a depletion solver to determine the change in nuclide composition at the end of each time step, and (3) a mechanics code to determine any structural impact due to a criticality event. Future research and development works include identifying/developing a modern two-phase thermal-hydraulics code and developing an approach to solve fast neutronic transients. The goal of this multiphysics framework is to determine the feasibility of direct disposal of currently loaded SNF canisters by including or excluding a criticality event from a repository performance analysis framework in terms of consequences. The revision 1 to this report includes extending Terrenus to a 17 x 17 pressurized water reactor (PWR) fuel assembly. We also investigated the phenomena necessary to quench a critical reaction, and investigated the water level necessary to achieve criticality in a typical canister. Finally, we describe the initial implementation of a critical power search capability.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

A Misload Analysis Methodology Supporting Criticality Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations

This paper presents an assembly misload analysis methodology developed to support criticality safety analysis of spent nuclear fuel (SNF) dual-purpose canisters (DPCs) using as-loaded configurations. The misload analysis approach is based on Interim Staff Guidance 8 “Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Casks” (ISG 8 rev. 3), but extended to support as-loaded configurations. The two misload scenarios analyzed included; (1) the correct assemblies are selected from the pool but placed incorrectly into the most reactive configuration inside the canister, and (2) the incorrect, most reactive assembly/assemblies in the pool is/are placed into the most reactive position(s) in the canister. Results from this misload analysis approach can be combined with misload probability to support criticality safety assessment of SNF during storage, transportation, and disposal. The misload analysis has been applied to 67 loaded DPCs at two sites using a disposal scenario. The analyzed sites include both PWR and BWR reactors and two canister variants—MPC-32 and MPC-68.

Liljenfeldt, Henrik↗
DOE OSTI2019

Criticality Safety Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations

Dual purpose canisters (DPCs) used for storage and transportation of spent nuclear fuel (SNF) are typically designed and evaluated using bounding (enveloping) fuel characteristics such as fuel type, fuel dimensions, initial enrichment, discharge burnup, and cooling time. This is a design basis, bounding licensing approach for SNF storage and transportation systems, as licensing and supporting safety analysis reviews are performed prior to the actual fuel loading. The bounding fuel characteristics for a system are developed by fully utilizing the regulatory and regulators recommended safety limits such as neutron multiplication factor (keff) approaching 0.95 to maximize the system utilizations. In reality, there are wide variations in SNF assembly burnups, initial enrichments, and cooling times. Therefore, dry storage systems are typically loaded with assemblies that satisfy the bounding fuel characteristics defined in the certificate of compliance (CoC), with some amount of unquantified and uncredited margin. This paper presents an as-loaded canister-specific criticality analysis approach for quantifying inherent uncredited margins in already loaded DPCs. The as-loaded analysis approach has been implemented in a new SNF management and analysis tool - The Used Nuclear Fuel-Storage, Transportation, and Disposal Analysis Resource and Data System (UNF ST&DARDS). The paper presents as-loaded criticality analysis of 616 canisters at 28 US reactor sites. Additionally, the paper discusses as-loaded analysis methodology validation approach using detailed reactor operational and fuel design data.

Banerjee, Kaushik↗
DOE OSTI2019

Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems

Simulations of neutron and photon transport using the Shift Monte Carlo radiation transport code are compared with experimental measurements and their corresponding benchmark simulations from several sets of experiments. Overall, Shift results match the calculations made by the benchmark teams quite well and match the measured values, which typically have large uncertainties, fairly well. A variety of attenuation/scattering problems are examined, as well as a streaming problem and a skyshine problem.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2019

Detailed Radiation Dose Rate Evaluations of Commercial Spent Nuclear Fuel Canisters

Electronic devices that are being designed for continuous monitoring of spent nuclear fuel (SNF) canister internal integrity may be subjected to very high radiation levels depending on their placement. Components of electronic devices (e.g., silicon semiconductors, optical glasses, insulators) have a limited tolerance to ionizing radiation. For selected locations on the inner and outer surfaces of a representative dry storage pressurized water reactor (PWR) SNF canister and a representative dry storage boiling water reactor (BWR) SNF canister, this paper provides (1) the dose rate in silicon as a function of decay time and (2) the time-integrated dose in silicon. The analyzed decay time interval is from 5 to 70 years after fuel discharge. Each representative canister contained identical SNF assemblies with bounding radiation sources. Surface dose rates varied significantly as a function of location and SNF assembly decay time. At a 5-year decay time, the estimated maximum dose rate values were 480 Gy/h (PWR canister) and ~366 Gy/h (BWR canister), and the estimated minimum dose rate was ~0.2 Gy/h for both canisters. Over a 65-year period, the dose rate decreased by a factor between 13 and 580, depending on location. The total dose over a time interval could be very large (e.g., estimated maximum value over a 5-year interval is 1.5E+07 Gy) depending on location and the time interval over which dose is accumulated.

Radulescu, Georgeta↗
DOE OSTI2019

Dose to Cementitious Material for Moderator Exclusion in a Spent Nuclear Fuel Canister During a Repository Timeframe

One of the concerns regarding direct disposal of spent nuclear fuel (SNF) dual-purpose canisters (DPCs) currently in dry storage is criticality during disposal time frames (e.g., 10,000 years or more). Preconditioning DPCs with appropriate filler materials (e.g., cementitious materials, low-melting metals) before disposal could prevent post-closure criticality by means of moderator displacement. However, potential radiolysis of the filler material by ionizing radiation and release of reactive chemical species over repository time frames may negatively impact the mechanical and chemical properties of the filler materials. Evaluation of the energy deposited in candidate filler materials by SNF radiation is essential for the calculation of radiolytic species. This paper provides an evaluation of the total energy deposited by gamma and neutron radiation in a candidate filler material over 10,000 years for a representative pressurized water reactor SNF DPC. The canister is assumed to contain identical SNF assemblies with a burnup value of 55 GWd/MTU, which is the bounding burnup value for more than 95% of the SNF inventory discharged from 1968 to 2013. The evaluated energy deposited per unit volume of filler material between 10 years and 10,000 years after fuel discharge is approximately 9.3E+23 eV/cm3. Gas production from radiolysis was not evaluated and may be revisited in future work. Radiolysis may be the principal gas generation mechanism for a cementitious system.

Radulescu, Georgeta↗
DOE OSTI2019

Dual-purpose canister filling simulation and validation: Part II- Validation

A mock up spent fuel canister test section is designed and built at Oak Ridge National Laboratory to support the R&D efforts on the direct disposal of dual purpose spent fuel canisters. The objective of the experimental testing is to investigate feasibility and to identify the unknown to gain confidence in the filing process and to validate computational models designed to simulate the process. The scope of the initial studies is to validate single-physics scaled testing of flow simulation to determine injectability, void filling, filling time, and filling method (gravity vs. pump).

Cetiner, Nesrin↗