1
|
Reger D, Merzari E, Balestra P, Schunert S, Hassan Y, Yuan H. An improved pressure drop correlation for modeling localized effects in a pebble bed reactor. Nuclear Engineering and Design 2023. [DOI: 10.1016/j.nucengdes.2022.112123] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/26/2022]
|
2
|
Calvin OW, Gale MD, Schunert S. Evaluating Quantities of Interest Other Than Nuclide Densities in the Bateman Equations. NUCL SCI ENG 2023. [DOI: 10.1080/00295639.2022.2161802] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 02/15/2023]
Affiliation(s)
- Olin W. Calvin
- Idaho National Laboratory, Reactor System Design and Analysis Division, 1955 North Fremont Avenue, MS 1347, Idaho Falls, Idaho 83415
- University of Idaho, Idaho Falls, Center for Advanced Energy Studies, 995 MK Simpson Boulevard, Idaho Falls, Idaho 83401
| | - Micah D. Gale
- Idaho National Laboratory, Reactor System Design and Analysis Division, 1955 North Fremont Avenue, MS 1347, Idaho Falls, Idaho 83415
| | - Sebastian Schunert
- Idaho National Laboratory, Reactor System Design and Analysis Division, 1955 North Fremont Avenue, MS 1347, Idaho Falls, Idaho 83415
| |
Collapse
|
3
|
Reger D, Merzari E, Balestra P, Schunert S, Hassan Y, Yuan H, Lan YH, Fischer P, Min M. Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors. NUCL TECHNOL 2022. [DOI: 10.1080/00295450.2022.2108688] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/14/2022]
Affiliation(s)
- David Reger
- Pennsylvania State University, University Park, Pennsylvania 16803
| | - Elia Merzari
- Pennsylvania State University, University Park, Pennsylvania 16803
| | | | | | | | - Haomin Yuan
- Argonne National Laboratory, Lemont, Illinois 60439
| | | | - Paul Fischer
- Argonne National Laboratory, Lemont, Illinois 60439
| | - Misun Min
- Argonne National Laboratory, Lemont, Illinois 60439
| |
Collapse
|
4
|
Freile R, Tano M, Balestra P, Schunert S, Kimber M. Improved natural convection heat transfer correlations for reactor cavity cooling systems of high-temperature gas-cooled reactors: From computational fluid dynamics to Pronghorn. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108547] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
|
5
|
Ortensi J, Baker BA, Johnson MP, Wang Y, Labouré VM, Schunert S, Gleicher FN, DeHart MD. Validation of the Griffin application for TREAT transient modeling and simulation. Nuclear Engineering and Design 2021. [DOI: 10.1016/j.nucengdes.2021.111478] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
|
6
|
Novak A, Schunert S, Carlsen R, Balestra P, Slaybaugh R, Martineau R. Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107968] [Citation(s) in RCA: 10] [Impact Index Per Article: 3.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
|
7
|
Wang Y, Schunert S, Ortensi J, Laboure V, DeHart M, Prince Z, Kong F, Harter J, Balestra P, Gleicher F. Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application. NUCL TECHNOL 2021. [DOI: 10.1080/00295450.2020.1843348] [Citation(s) in RCA: 8] [Impact Index Per Article: 2.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
Affiliation(s)
- Yaqi Wang
- Idaho National Laboratory, Nuclear Engineering Methods Development, Idaho Falls, Idaho
| | - Sebastian Schunert
- Idaho National Laboratory, Nuclear Engineering Methods Development, Idaho Falls, Idaho
| | - Javier Ortensi
- Idaho National Laboratory, Reactor Physics Design and Analysis, Idaho Falls, Idaho
| | - Vincent Laboure
- Idaho National Laboratory, Reactor Physics Design and Analysis, Idaho Falls, Idaho
| | - Mark DeHart
- Idaho National Laboratory, Reactor Physics Design and Analysis, Idaho Falls, Idaho
| | - Zachary Prince
- Idaho National Laboratory, Nuclear Engineering Methods Development, Idaho Falls, Idaho
| | - Fande Kong
- Idaho National Laboratory, Computational Frameworks, Idaho Falls, Idaho
| | - Jackson Harter
- Idaho National Laboratory, Reactor Physics Design and Analysis, Idaho Falls, Idaho
| | - Paolo Balestra
- Idaho National Laboratory, Nuclear Engineering Methods Development, Idaho Falls, Idaho
| | - Frederick Gleicher
- Idaho National Laboratory, Reactor Physics Design and Analysis, Idaho Falls, Idaho
| |
Collapse
|
8
|
Novak AJ, Carlsen RW, Schunert S, Balestra P, Reger D, Slaybaugh RN, Martineau RC. Pronghorn: A Multidimensional Coarse-Mesh Application for Advanced Reactor Thermal Hydraulics. NUCL TECHNOL 2021. [DOI: 10.1080/00295450.2020.1825307] [Citation(s) in RCA: 6] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
Affiliation(s)
- A. J. Novak
- University of California Berkeley, Department of Nuclear Engineering, 3115 Etcheverry Hall, Berkeley, California 94720
| | | | - S. Schunert
- Idaho National Laboratory, Idaho Falls, Idaho
| | - P. Balestra
- Idaho National Laboratory, Idaho Falls, Idaho
| | - D. Reger
- Pennsylvania State University, Department of Nuclear Engineering, University Park, Pennsylvania
| | - R. N. Slaybaugh
- University of California Berkeley, Department of Nuclear Engineering, 3115 Etcheverry Hall, Berkeley, California 94720
| | | |
Collapse
|
9
|
Ortensi J, Wang Y, Labouré V, Gleicher FN, Schunert S, DeHart MD. IMPROVEMENTS TO THE MODELING OF THE TREAT REACTOR AND EXPERIMENTS. EPJ Web Conf 2021. [DOI: 10.1051/epjconf/202124706025] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
This paper summarizes the latest improvements and lessons learned from the modeling and simulation of the transient test reactor at Idaho National Laboratory using the MAMMOTH reactor physics application. MAMMOTH is a MOOSE-based, Finite Element Method application that specializes in the analysis of the spatial dynamics behavior of nuclear reactors. Since early 2018 several transient tests have been conducted at TREAT, thus providing the opportunity to apply and benchmark modern modeling and simulation tools. MAMMOTH was used to provide predictions of the power coupling factor between the core and the experiment for various experiments. Even though the power coupling factor predictions agree very well with the experimental data, within the bounds of the experimental uncertainty, one shortcoming was the underprediction of the total energy deposited in the core and experiment. Determination of the sources for this discrepancy is ongoing, but several key problems have been identified and resolved, thus providing valuable insights for future research. This paper discusses several of these lessons learned. First, the heat capacity data for the TREAT fuel has some significant problems due to limitations of the measurement techniques used circa 1960s. The sensitivity of the peak power and the total energy deposition to various representations of the heat capacity is approximately 5%. Second, the effects of the biological shield and thermal column on the modeling of the core are non-negligible, since they affect the mean generation time and the effective reflection of neutrons back into the core, which is suspected to be important during the core heat up. Matching the reactor period resolves the fact that the reduced spatial domain used in the MAMMOTH model underpredicts the mean generation time. The neutron reflection from these regions is marginally improved with the use of an albedo boundary condition. Third, modeling of the control rod movement with a multi-scheme method is introduced and its current limitations are exposed. Fourth, we explore the effects of using a homogenized model with Superhomogenization equivalence and how that differs from fully heterogeneous simulations. Finally, the energy condensation effects for this graphite core are significant. Solutions with 10 and 26 energy groups show the benefits of using a finer coarse group structure.
Collapse
|
10
|
Balestra P, Schunert S, Carlsen RW, Novak AJ, DeHart MD, Martineau RC. PBMR-400 BENCHMARK SOLUTION OF EXERCISE 1 AND 2 USING THE MOOSE BASED APPLICATIONS: MAMMOTH, PRONGHORN. EPJ Web Conf 2021. [DOI: 10.1051/epjconf/202124706020] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
High temperature gas cooled reactors (HTGR) are a candidate for timely Gen-IV reactor technology deployment because of high technology readiness and walk-away safety. Among HTGRs, pebble bed reactors (PBRs) have attractive features such as low excess reactivity and online refueling. Pebble bed reactors pose unique challenges to analysts and reactor designers such as continuous burnup distribution depending on pebble motion and recirculation, radiative heat transfer across a variety of gas-filled gaps, and long design basis transients such as pressurized and depressurized loss of forced circulation. Modeling and simulation is essential for both the PBR’s safety case and design process. In order to verify and validate the new generation codes the Nuclear Energy Agency (NEA) Data bank provide a set of benchmarks data together with solutions calculated by the participants using the state of the art codes of that time. An important milestone to test the new PBR simulation codes is the OECD NEA PBMR-400 benchmark which includes thermal hydraulic and neutron kinetic standalone exercises as well as coupled exercises and transients scenarios. In this work, the reactor multiphysics code MAMMOTH and the thermal hydraulics code Pronghorn, both developed by the Idaho National Laboratory (INL) within the multiphysics object-oriented simulation environment (MOOSE), have been used to solve Phase 1 exercises 1 and 2 of the PBMR-400 benchmark. The steady state results are in agreement with the other participants’ solutions demonstrating the adequacy of MAMMOTH and Pronghorn for simulating PBRs.
Collapse
|
11
|
|
12
|
Labouré V, Wang Y, Ortensi J, Schunert S, Gleicher F, DeHart M, Martineau R. Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.01.003] [Citation(s) in RCA: 11] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
|
13
|
Zabriskie A, Schunert S, Schwen D, Ortensi J, Baker B, Wang Y, Laboure V, DeHart M, Marcum W. A Coupled Multiscale Approach to TREAT LEU Feedback Modeling Using a Binary-Collision Monte-Carlo–Informed Heat Source. NUCL SCI ENG 2018. [DOI: 10.1080/00295639.2018.1528802] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
Affiliation(s)
- Adam Zabriskie
- Oregon State University, School of Nuclear Science and Engineering, 1500 SW Jefferson Street, Corvallis, Oregon 97331
| | - Sebastian Schunert
- Idaho National Laboratory, Nuclear Science and Technology Directorate, 2525 Fremont Avenue, Idaho Falls, Idaho 83415
| | - Daniel Schwen
- Idaho National Laboratory, Nuclear Science and Technology Directorate, 2525 Fremont Avenue, Idaho Falls, Idaho 83415
| | - Javier Ortensi
- Idaho National Laboratory, Nuclear Science and Technology Directorate, 2525 Fremont Avenue, Idaho Falls, Idaho 83415
| | - Benjamin Baker
- Idaho National Laboratory, Nuclear Science and Technology Directorate, 2525 Fremont Avenue, Idaho Falls, Idaho 83415
| | - Yaqi Wang
- Idaho National Laboratory, Nuclear Science and Technology Directorate, 2525 Fremont Avenue, Idaho Falls, Idaho 83415
| | - Vincent Laboure
- Idaho National Laboratory, Nuclear Science and Technology Directorate, 2525 Fremont Avenue, Idaho Falls, Idaho 83415
| | - Mark DeHart
- Idaho National Laboratory, Nuclear Science and Technology Directorate, 2525 Fremont Avenue, Idaho Falls, Idaho 83415
| | - Wade Marcum
- Oregon State University, School of Nuclear Science and Engineering, 1500 SW Jefferson Street, Corvallis, Oregon 97331
| |
Collapse
|
14
|
|
15
|
Schunert S, Azmy Y. Comparison of Spatial Discretization Methods for Solving the SN Equations Using a Three-Dimensional Method of Manufactured Solutions Benchmark Suite with Escalating Order of Nonsmoothness. NUCL SCI ENG 2017. [DOI: 10.13182/nse14-77] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Sebastian Schunert
- North Carolina State University, Department of Nuclear Engineering, 2500 Stinson Drive, 3140 Burlington Engineering Labs, Raleigh, North Carolina 27695-7909
| | - Yousry Azmy
- North Carolina State University, Department of Nuclear Engineering, 2500 Stinson Drive, 3140 Burlington Engineering Labs, Raleigh, North Carolina 27695-7909
| |
Collapse
|
16
|
|
17
|
Affiliation(s)
- Sebastian Schunert
- North Carolina State University, Department of Nuclear Engineering 2500 Stinson Drive, 3140 Burlington Eng. Labs, Raleigh, North Carolina 27695-7909
| | - Yousry Azmy
- North Carolina State University, Department of Nuclear Engineering 2500 Stinson Drive, 3140 Burlington Eng. Labs, Raleigh, North Carolina 27695-7909
| |
Collapse
|