Research output per year
Research output per year
- 1 - 50 out of 189 results
Search results
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2024
Application of a Qualitative Risk-Informed, Performance-Based Approach for the MARVEL Microreactor at the Idaho National Laboratory
Gerstner, D., Andrus, J., Foley, A. & Reiss, T., 2024, Proceedings of Advanced Reactor Safety, ARS 2024. American Nuclear Society, p. 254-263 10 p. (Proceedings of Advanced Reactor Safety, ARS 2024).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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CFR-ICL: Cascade-Forward Refinement with Iterative Click Loss for Interactive Image Segmentation
Sun, S., Xian, M., Xu, F., Capriotti, L. & Yao, T., Mar 25 2024, Technical Tracks 14. Wooldridge, M., Dy, J. & Natarajan, S. (eds.). 5 ed. Association for the Advancement of Artificial Intelligence, p. 5017-5024 8 p. (Proceedings of the AAAI Conference on Artificial Intelligence; vol. 38, no. 5).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access5 Scopus citations -
Designing a Nuclear Thermal Propulsion Experiment for Irradiation in a Nuclear Reactor
Veselka, H. & Fradeneck, A., 2024, Proceedings of Nuclear and Emerging Technologies for Space, NETS 2024. American Nuclear Society, p. 308-315 8 p. (Proceedings of Nuclear and Emerging Technologies for Space, NETS 2024).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Fast and thermal neutron spectrum dosimetry measurements in the Advanced Test Reactor large-B and small-I positions following the sixth core internals change-out
Reichenberger, M., Maile, A., Johnson, M., Norman, D., Bays, S., McCary, K. & Manwaring, N., Nov 11 2024, ISRD 17 - International Symposium on Reactor Dosimetry (Part II). Frajtag, P., hornton, D. & Wagemans, J. (eds.). EDP Sciences, 06004. (EPJ Web of Conferences; vol. 308).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access -
Fostering Energy Justice: Engaging Communities for a Sustainable Nuclear Future
Romine, P., Hozien, W., Egarievwe, S. U., Sarwat, A., Dulloo, A. R. & Dickmann, E. M., 2024, Pacific Basin Nuclear Conference, PBNC 2024. American Nuclear Society, p. 602-611 10 p. (Pacific Basin Nuclear Conference, PBNC 2024).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Friction Corrections to Improve Accuracy of Cladding Strength Measurements from the Ring Tension Test
Hansen, R. S., Kamerman, D. W., Petersen, P. G. & Cappia, F., 2024, Proceedings of the 2023 Water Reactor Fuel Performance Meeting - WRFPM 2023. Liu, J. & Jiao, Y. (eds.). Springer Science and Business Media Deutschland GmbH, p. 317-329 13 p. (Springer Proceedings in Physics; vol. 299).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
1 Scopus citations -
Lanthanide Separation from Uranium via Molten Zone Refinement
Zirker, D., Horvath, D., Childs, M. & Yoo, T. S., Oct 10 2024, Pacific Basin Nuclear Conference, PBNC 2024. American Nuclear Society, p. 242-251 10 p. (Pacific Basin Nuclear Conference, PBNC 2024).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Overview of the Neutron Radiography Reactor (NRAD) for Neutron Imaging and In-Core Experiment Capabilities at Idaho National Laboratory
Xu, P., Craft, A. & Ruddell, M., Nov 17 2024, Proceedings of the Radiation Protection and Shielding Division 2024, RPSD 2024. American Nuclear Society, p. 100-101 2 p. (Proceedings of the Radiation Protection and Shielding Division 2024, RPSD 2024).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Oxide Growth Predictions During an Advanced Test Reactor (ATR) Powered Axial Locator Mechanism (PALM) Cycle
Barney, J. W., Choe, D. O. & Kilby, S. M., Feb 5 2024, ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE). American Society of Mechanical Engineers (ASME), V007T08A085. (ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE); vol. 7).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Photonuclear Reaction Yields and Excitation Functions
Cardenas, E., Wells, D., Dale, D., Forest, T. & Reichenberger, M., Jul 25 2024, Proceedings of the INMM 2024 Annual Meeting.Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Preliminary Analysis of a Nuclear-Grade Sandwich Composite for Transportable Microreactor Shielding
Stewart, R. H., Bays, S. E., Zabriskie, A. X., Zelina, J. N., Ougouag, A. M. & O'Brien, R. C., 2024, Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024. American Nuclear Society, p. 326-335 10 p. (Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
2 Scopus citations -
Process Improvements For Pu-238 Production at Idaho National Laboratory
Green, W. S., Zillmer, A. J., Mitchell, J. R., Rosvall, E., Grayson, B., Fradeneck, A. D., Geddes, K. M., Paulsen, R. & Lower, J. D., May 8 2024, Proceedings of Nuclear and Emerging Technologies for Space, NETS 2024. American Nuclear Society, p. 523-528 6 p. (Proceedings of Nuclear and Emerging Technologies for Space, NETS 2024).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access -
Pu-238 Production Progress at INL From December 2022 to December 2023
Green, W. S., Mitchell, J. R., Rosvall, E. S., Grayson, B. J., Marlow, R. L., Fradeneck, A. D., Foster, J. K., Geddes, K. M., Hill, M. A., O'Donnell Jr, P. F. & Zillmer, A. J., May 8 2024, Nuclear and Emerging Technologies for Space (NETS 2024).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
1 Scopus citations -
Qualifying the Instrument Thimble 11 Position in the Advanced Test Reactor Critical
Ottaway, D. G., McCary, K. M., Norman, D. R. & Reichenberger, M. A., Nov 17 2024, Proceedings of the Radiation Protection and Shielding Division 2024, RPSD 2024. American Nuclear Society, p. 85-88 4 p. (Proceedings of the Radiation Protection and Shielding Division 2024, RPSD 2024).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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2023
Considerations for the Risk-Informed Performance-Based Regulatory Treatment of Non-Core Sources of Radioactivity for Advanced Reactors
Grabaskas, D., Chen, B., Ferrara, S., Christensen, J. & Andrus, J., 2023, Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023. American Nuclear Society, p. 178-187 10 p. (Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Microstructurally Validated Stable and Predictable Swelling in Low-Enriched Uranium Monolithic U-10Mo Fuel Mini-Plates
Hanson, W., Salvato, D., Robinson, A., Lybeck, N., Trowbridge, T., Di Lemma, F., Keiser, D., Marshall, M., Giglio, J., Cole, J. & Jue, J.-F., Nov 15 2023, Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC 2023).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Natural Language Processing-Enhanced Nuclear Industry Operating Experience Data Analysis: Aggregation and Interpretation of Multi-Report Analysis Results
Zhang, S., Xu, F., Ma, Z. & Xian, M., 2023, Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023. American Nuclear Society, p. 230-239 10 p. (Proceedings of 18th International Probabilistic Safety Assessment and Analysis, PSA 2023).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
2 Scopus citations -
Primary Coolant Apparatus Test (PCAT): an Experimental Facility for MARVEL Microreactor
Parisi, C., Yoon, S., Baily, C., Grover, B., Arafat, Y. & Kim, S. J., 2023, Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. American Nuclear Society, p. 1864-1877 14 p. (Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
1 Scopus citations -
Progress on Pu-238 Production at Idaho National Laboratory From February 2022 to December 2022
Green, W. S., Lower, J. D., Mitchell, J. R., Grayson, B. J., Rosvall, E. S., Fradeneck, A. D., Fishler, J. D., Marlow, R. L., Hill, M. A. & Zillmer, A. J., May 9 2023, Proceedings of Nuclear and Emerging Technologies for Space, NETS 2023. American Nuclear Society, p. 262-267 6 p. (Proceedings of Nuclear and Emerging Technologies for Space, NETS 2023).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access1 Scopus citations -
Sampling of Spent Nuclear Fuel Using a Rotary Riffler
Karlsson, T., Malewitz, T. J., Sanders, J., King, J., Mohr, B., Lecrivain, L. & Warmann, S., Nov 15 2023, Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC 2023).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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The Next Generation Radioisotope Thermoelectric Generator-Power for Future Deep Space Missions
Weaver, A., Demichael, T., Woytach, J., Fleurial, J. P., Birch, J. & Davis, S., May 15 2023, IEEE Aerospace Conference Proceedings. IEEE Computer Society, (IEEE Aerospace Conference Proceedings; vol. 2023-March).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
7 Scopus citations -
The Next Generation Radioisotope Thermoelectric Generator Project -- Overview and Progress Status
Tofil, T. A., Demichael, T., Woytach, J., Fleurial, J. P., Birch, J. & Davis, S., May 11 2023, Proceedings of Nuclear and Emerging Technologies for Space, NETS 2023. American Nuclear Society, p. 268-275 8 p. (Proceedings of Nuclear and Emerging Technologies for Space, NETS 2023).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
3 Scopus citations -
2022
Considerations for Nuclear Thermal Propulsion Reactor Technology Readiness Level Advancement
Palomares, K., Werner, J., Todosow, M. & Lenox, K., 2022, Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022. American Nuclear Society, p. 348-356 9 p. (Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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From FUMAC and ACTOF to ATF-TS: Contribution of IAEA CRPs to Advanced Technology Fuel Testing, Modelling and Simulation
Zhang, J., Xu, P., Sim, K. S., Veshchunov, M. & Khaperskaia, A., 2022, Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference. American Nuclear Society, p. 382-389 8 p. (Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
1 Scopus citations -
Initial Post-irradiation optical microscopy results from priority plates in the EMPIrE fuel test
Hanson, W., Robinson, A., Keiser, D., Glagolenko, I., Ye, B., Mei, Z. G., Jamison, L. & Hofman, G. L., May 31 2022, Fuel Cycle from Front End to Back End.. p. 286-294 8 p.Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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INL Operations Improvements of Nuclear Enabled Missions for NASA
Clarke, E. & Johnson, S., 2022, Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022. American Nuclear Society, p. 76-79 4 p. (Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Micro-Tensile Testing of Chromium Coated Zirconium Cladding
Frazer, D., Howard, C., Wang, Y., Murray, D., Teng, F., Judge, C., Walters, J., Wright, J. & Olson, L., 2022, AMPP Conference Papers, 20th International Conference On Environmental Degradation of Materials in Power Systems - Water Reactors.Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Overview of Light Weight Radioisotope Heater Unit (LWRHU) User's Guide
Zillmer, A. & Gates, A., 2022, Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022. American Nuclear Society, p. 634-638 5 p. (Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access -
Progress on Pu-238 Production at Idaho National Laboratory From March 2021 to February 2022
Zillmer, A., Green, W., Tyler, C., Lower, J., Mitchell, J., Grayson, B., Rosvall, E., Fradeneck, A., Fishler, J., Reeder, D., Marlow, R., Hill, M., O'Donnell, P., Peterson-Droogh, J. & Howard, R., 2022, Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022. American Nuclear Society, p. 392-396 5 p. (Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access1 Scopus citations -
Pu-238 Production Calculator and Estimation Tool in the Advanced Test Reactor
Weaver, D. & Zillmer, A., May 2022, Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022. American Nuclear Society, p. 388-391 4 p. (Proceedings of Nuclear and Emerging Technologies for Space, NETS 2022).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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THE U.S. ACCIDENT TOLERANT FUELS PROGRAM - Transforming the Future of LWR Fuels
Goldner, F., McCaughey, W., Wachs, D., Kamerman, D., Jensen, C., Woolstenhulme, N., Cappia, F., Schulthess, J., Medvedev, P., Nelson, A., Capps, N., Linton, K., Harp, J., Massey, C., Saleh, T., Eftink, B. & White, J., 2022, Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference. American Nuclear Society, p. 90-97 8 p. (Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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U.S. Perspective On Harvesting And Archiving Of Aged Components To Improve Materials Degradation Knowledge And Inform Aging Management
Judge, C., 2022, AMPP Conference Papers, 20th International Conference On Environmental Degradation of Materials in Power Systems - Water Reactors.Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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2021
CONCEPTUAL DESIGN OF TEMPERATURE-CONTROLLED FUELED-SALT IRRADIATION EXPERIMENT TO SUPPORT DEMONSTRATION OF ADVANCED NUCLEAR REACTORS
Abou-Jaoude, A., Chandler, J., Core, G., Davies, K., Downey, C., Phillips, W., Tan, C. & Wilson, S., 2021, Energy. American Society of Mechanical Engineers (ASME), V08BT08A014. (ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE); vol. 8B-2021).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access4 Scopus citations -
DEVELOPMENT OF A GRIFFIN REACTOR PHYSICS ANALYSIS CODE MODEL FOR THE VERSATILE TEST REACTOR
Martin, N., Stewart, R., Xu, Z. & Bays, S., 2021, Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021. American Nuclear Society, p. 778-787 10 p. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
1 Scopus citations -
DEVELOPMENT OF A THERMAL HYDRAULIC MODEL FOR THE VERSATILE TEST REACTOR USING THE CTF SUBCHANNEL CODE
Takasugi, C., Martin, N., Yoon, S. J., Bays, S., Avramova, M. & Ivanov, K., 2021, Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021. American Nuclear Society, p. 2274-2283 10 p. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Fundamental Understanding of Nb Effect on Corrosion Mechanisms of Irradiated Zr-Nb Alloys
Yu, Z., Moorehead, M., Borrel, L., Hu, J., Bachhav, M. & Couet, A., 2021, Zirconium in the Nuclear Industry: 19th International Symposium. Motta, A. T. & Yagnik, S. K. (eds.). ASTM International, p. 669-695 27 p. (ASTM Special Technical Publication; vol. STP 1622).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
5 Scopus citations -
MULTIPHYSICS SIMULATION OF THE MOLTEN SALT FAST REACTOR USING GRIFFIN AND PRONGHORN
Balestra, P., Abou-Jaoude, A., Martin, N., Schunert, S., Hermosillo, A. & Wang, Y., 2021, Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021. American Nuclear Society, p. 2382-2396 15 p. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Testing of an Ultrasonic Thermometer Developed at the Idaho National Laboratory
Daw, J., Hone, L. & Woodbury, K., May 17 2021, I2MTC 2021 - IEEE International Instrumentation and Measurement Technology Conference, Proceedings. Institute of Electrical and Electronics Engineers Inc., 9459867. (Conference Record - IEEE Instrumentation and Measurement Technology Conference; vol. 2021-May).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
2 Scopus citations -
2020
Analysis of Preliminary PIE Results for PVD Coated U-7Mo Dispersion Fuel Plates Irradiated in the EMPIrE Experiment
Hofman, G. L., Jamison, L., Ye, B., Mei, Z. G., Yacout, A. M., Robinson, A., Hanson, W., Nielsen, J., Keiser, D. & Leenaers, A., 2020, Fuel Cycle from Front End to Back End. p. 27-31 4 p.Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Anatomical fraction segmentation in the biomass bales
Kancharla, R. R., Smith, W. A., Barney Smith, E. H. & Klinger, J. L., 2020, 2020 Virtual AIChE Annual Meeting. American Institute of Chemical Engineers, (AIChE Annual Meeting, Conference Proceedings; vol. 2020-November).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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A SENSITIVITY STUDY OF SODIUM HEAT PIPES FOR MICROREACTOR APPLICATIONS
Turner, C. & Guillen, D. P., 2020, ATH 2020 - International Topical Meeting on Advances in Thermal Hydraulics. American Nuclear Society, p. 143-156 14 p. (ATH 2020 - International Topical Meeting on Advances in Thermal Hydraulics).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
2 Scopus citations -
Axial flux profile in the advanced test reactor
Manwaring, N. & Reichenberger, M., 2020, International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020. Margulis, M. & Blaise, P. (eds.). EDP Sciences - Web of Conferences, p. 1610-1618 9 p. (International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020; vol. 2020-March).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access -
Commissioning of the nddl-40 micro-channel plate neutron detector system at oregon state university
Boulton, N. M., Reese, S. R. & Craft, A. E., 2020, Neutron Radiography - 11th World Conference on Neutron Radiography, WCNR 2018. Salvemini, F. & Bevitt, J. J. (eds.). Association of American Publishers, p. 86-91 6 p. (Materials Research Proceedings; vol. 15).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access -
Conversion from film based transfer method neutron radiography to computed radiography for post irradiation examination of nuclear fuels
Papaioannou, G. C., Craft, A. E. & Ruddell, M. A., 2020, Neutron Radiography - 11th World Conference on Neutron Radiography, WCNR 2018. Salvemini, F. & Bevitt, J. J. (eds.). Association of American Publishers, p. 136-141 6 p. (Materials Research Proceedings; vol. 15).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access5 Scopus citations -
Epithermal neutron radiography and tomography on large and strongly scattering samples
Schillinger, B. & Craft, A., 2020, Neutron Radiography - 11th World Conference on Neutron Radiography, WCNR 2018. Salvemini, F. & Bevitt, J. J. (eds.). Association of American Publishers, p. 142-148 7 p. (Materials Research Proceedings; vol. 15).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access3 Scopus citations -
Evolution of space reactor qualification methods and a path forward for new space reactors under consideration
Zillmer, A., Rao, D. & Johnson, S., Mar 2020, 2020 IEEE Aerospace Conference, AERO 2020. IEEE Computer Society, 9172482. (IEEE Aerospace Conference Proceedings).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access1 Scopus citations -
Fabrication and assembly of the first accident tolerant fuel concept for treat testing
Woolum, C., Devin Imholte, D., Fleming, A., Kamerman, D. & Tritthart, K., 2020, Materials and Fabrication. American Society of Mechanical Engineers (ASME), v006t06a078. (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; vol. 6).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
1 Scopus citations -
First neutron computed tomography with digital neutron imaging systems in a high-radiation environment at the 250 kw neutron radiography reactor at idaho national laboratory
Craft, A., Schillinger, B., Chuirazzi, W., Papaioannou, G., Smolinski, A. & Boutlon, N., 2020, Neutron Radiography - 11th World Conference on Neutron Radiography, WCNR 2018. Salvemini, F. & Bevitt, J. J. (eds.). Association of American Publishers, p. 42-47 6 p. (Materials Research Proceedings; vol. 15).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access2 Scopus citations -
Gamma discriminating scintillation screens for digital transfer method neutron imaging
Craft, A., Grünzweig, C., Morgano, M., Chuirazzi, W. & Lehmann, E., 2020, Neutron Radiography - 11th World Conference on Neutron Radiography, WCNR 2018. Salvemini, F. & Bevitt, J. J. (eds.). Association of American Publishers, p. 74-79 6 p. (Materials Research Proceedings; vol. 15).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access4 Scopus citations -
Quantitative crack analysis using indirect neutron radiography and neutron activation analysis with contrast enhancement agents
Jarmer, R., King, J., Craft, A. & O'Brien, R., 2020, Neutron Radiography - 11th World Conference on Neutron Radiography, WCNR 2018. Salvemini, F. & Bevitt, J. J. (eds.). Association of American Publishers, p. 165-173 9 p. (Materials Research Proceedings; vol. 15).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access2 Scopus citations