NSUF 10-234: Development and Validation of an ATR-C Radiation Transport Model
In this proposed collaboration between the University of Nevada, Las Vegas (UNLV), Idaho National Laboratory (INL), and Los Alamos National Laboratory (LANL), the UNLV Principle Investigator will supervise two graduate research assistants (GRA) who will develop and validate a radiation transport model of the Advanced Test Reactor Critical facility (ATR-C) for conducting and evaluating integral and critical benchmark experiments. In Phase I (Jan. 2010 to May 2011) the first student will use the existing MCNP5 Monte Carlo model of the ATR and geometric modeling methods, such as the Visual Editor or other conversion systems, to convert computer automated drawings (CAD) into components of surfaces, bodies, and cells to create the input file for the ATR-C model. The GRA will also verify that materials, components, and configurations in the model are consistent with the current physical condition of the ATR-C. Sensitivity studies will then be completed to determine biases and uncertainties expected because of approximations, unknown constituents, and/or uncertainties in components. In Phase II (June 2011 to Dec. 2012) the second GRA will design, fabricate, construct, and conduct experiments to validate the ATR-C model and demonstrate its usefulness for future cross-cutting fuel cycle R&D, criticality benchmark evaluations, etc. The UNLV graduate students will also contribute to the production of a draft PRIMER for use by others for modeling samples, detectors, or other items to be placed in criticality benchmark experiments in the ATR-C. UNLV will develop the MCNP model and validation experiments in accordance with guidelines in handbooks from the International Reactor Physics Experiment Evaluation Project and the International Criticality Safety Benchmark Evaluation Project. Period of Performance: Jan. 2010 to May 2011 Phase I: ATRC MCNP model development and sensitivity studies June 2011 to Dec. 2012 Phase II: ATR-C model validation experiments and evaluation The completion of this combined modeling and experimental project will contribute to the Department of Energy’s goals to develop new nuclear generation technologies and to maintain, enhance, and safeguard the U.S.’s nuclear infrastructure capabilities. Subsequent ATR-C experiments will support several DOE programs by providing a new cross-cutting facility accompanied by demonstrated modeling techniques and a standard radiation model/method for analyses of new integral cross section and benchmark experiments. The results of these efforts will subsequently assist in the expansion/diversity of domestic energy supplies via deployment in the next decade of advanced, proliferation-resistant fuel cycle technologies and in subsequent decades of advanced reactors (e.g. next-generation reactors) and fuel cycles (e.g. proliferation resistant recycling and/or thorium). In addition, increasing the nation’s infrastructural capabilities for critical experiments involving advanced materials will help universities, national laboratories, and private industry expand applications of nuclear energy and other nuclear programs (e.g. accelerators for transmutation, isotope production, etc.) to meet the Nation’s energy, environmental, medical research, space exploration, industrial, and national security needs. Finally, the research will foster new university-lab collaborations in support of criticality benchmark experiments while strengthening a growing graduate nuclear engineering program that is focused on nuclear criticality safety, recycling nuclear waste, and radiation detection and monitoring for national security.
Additional Info
| Field | Value |
|---|---|
| Abstract | In this proposed collaboration between the University of Nevada, Las Vegas (UNLV), Idaho National Laboratory (INL), and Los Alamos National Laboratory (LANL), the UNLV Principle Investigator will supervise two graduate research assistants (GRA) who will develop and validate a radiation transport model of the Advanced Test Reactor Critical facility (ATR-C) for conducting and evaluating integral and critical benchmark experiments. In Phase I (Jan. 2010 to May 2011) the first student will use the existing MCNP5 Monte Carlo model of the ATR and geometric modeling methods, such as the Visual Editor or other conversion systems, to convert computer automated drawings (CAD) into components of surfaces, bodies, and cells to create the input file for the ATR-C model. The GRA will also verify that materials, components, and configurations in the model are consistent with the current physical condition of the ATR-C. Sensitivity studies will then be completed to determine biases and uncertainties expected because of approximations, unknown constituents, and/or uncertainties in components. In Phase II (June 2011 to Dec. 2012) the second GRA will design, fabricate, construct, and conduct experiments to validate the ATR-C model and demonstrate its usefulness for future cross-cutting fuel cycle R&D, criticality benchmark evaluations, etc. The UNLV graduate students will also contribute to the production of a draft PRIMER for use by others for modeling samples, detectors, or other items to be placed in criticality benchmark experiments in the ATR-C. UNLV will develop the MCNP model and validation experiments in accordance with guidelines in handbooks from the International Reactor Physics Experiment Evaluation Project and the International Criticality Safety Benchmark Evaluation Project. Period of Performance: Jan. 2010 to May 2011 Phase I: ATRC MCNP model development and sensitivity studies June 2011 to Dec. 2012 Phase II: ATR-C model validation experiments and evaluation The completion of this combined modeling and experimental project will contribute to the Department of Energy’s goals to develop new nuclear generation technologies and to maintain, enhance, and safeguard the U.S.’s nuclear infrastructure capabilities. Subsequent ATR-C experiments will support several DOE programs by providing a new cross-cutting facility accompanied by demonstrated modeling techniques and a standard radiation model/method for analyses of new integral cross section and benchmark experiments. The results of these efforts will subsequently assist in the expansion/diversity of domestic energy supplies via deployment in the next decade of advanced, proliferation-resistant fuel cycle technologies and in subsequent decades of advanced reactors (e.g. next-generation reactors) and fuel cycles (e.g. proliferation resistant recycling and/or thorium). In addition, increasing the nation’s infrastructural capabilities for critical experiments involving advanced materials will help universities, national laboratories, and private industry expand applications of nuclear energy and other nuclear programs (e.g. accelerators for transmutation, isotope production, etc.) to meet the Nation’s energy, environmental, medical research, space exploration, industrial, and national security needs. Finally, the research will foster new university-lab collaborations in support of criticality benchmark experiments while strengthening a growing graduate nuclear engineering program that is focused on nuclear criticality safety, recycling nuclear waste, and radiation detection and monitoring for national security. |
| Award Announced Date | 2010-01-21T00:00:00 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Alina Zackrone |
| Irradiation Facility | None |
| PI | Denis Beller |
| PI Email | [email protected] |
| Project Type | Irradiation |
| RTE Number | 234 |