Abstract
The VENUS PWR Mockup Experiment is an important component of the Nuclear Regulatory Commission’s program goal of benchmarking reactor pressure vessel (RPV) fluence calculations in order to determine the accuracy to which RPV fluence can be computed. Of particular concern in this experiment is the accuracy of the source calculation near the core-baffle interface, which is the important region for contributing to RPV fluence.
Results indicate that the calculated neutron source distribution within the VENUS core agrees with the experimental measured values with an average error of less that 3%, except at the baffle corner, where the error is about 6%. Better agreement with the measured fission distribution was obtained with a detailed space- dependent cross-section weighting procedure for thermal cross sections near the core-baffle interface region. The maximum error introduced into the predicted RPV fluence due to source errors should be on the order of 5%.
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References
M.L. Williams, R.E. Maerker, F.W. Stallmann, and F.B.K. Kam, “Validation of Neutron Tranport Calculations in Benchmark Facilities for Improved Vessel Fluence Estimation,” Proc. of the 11th WRSR Information Meeting, Gaithersburg, MD, October 24–28, 1983, NUREG/CP-0048, Vols. 1–6, U.S. Nuclear Regulatory Commission, Washington, DC.
G. Minsart, Design Study of the Core Loading for the VENUS PWR Preseure Vessel Benchmark Facility, CEN/SCK, Mol, Report 380/82–27, October 5, 1982.
L. Leenders, “Definitions of Qualification of the Materials Used in the VENUS Configuration,” Correspondence from CEN/SCK in Mol, Belgium, to Oak Ridge National Laboratory, 1983.
W. E. Ford, III, C. C. Webster, and R. M. Westfall, A 218-Group Neutron Cross-Section Library in the AMPX Master Interface Format for Criticality Safety Studies, ORNL/CSD/TM-4, Oak Ridge National Laboratory, Oak Ridge, TN, July 1976.
N.M. Green et al., “AMPX: A Modular System for Multigroup Cross-Section Generation and Manipulation,” A Review of Multigroup Nuclear Cross-Section Processing, Proceedings of a Seminar-Workshop, Oak Ridge, TN, March 14–16, 1978.
L.M. Petrie, N.M. Greene, J.L. Lucius, and J.E. White, NITAWL: AMPX Module for Resonance Self-Shielding and Working Library Production, PSR- 63/AMPX-II, 1978.
L.M. Petrie and N.M. Greene, XSDRNPM-S: A One-Dimensional Discretes Ordinates Code for Transport Analysis, NUREG/CR-0200, Vol. 2, Section F3, ORNL/NUREG/CSD-2/V3/R1, U.S. Nuclear Regulatory Commission, Washington, DC, 1982.
W.A. Rhoades and R.L. Childs, An Updated Version of the DOT IV One- and Two-Dimensional Neutron/Photon Transport Code, ORNL-5851, Oak Ridge National Laboratory, Oak Ridge, TN, 1982.
M.L. Williams, R.E. Maerker, W.E. Ford III, and C.C. Webster, The ELXSIR Cross-Section Library for LWR Pressure Vessel Irradiation Studies, Electric Power Research Institute, EPRI report in press.
P. Morakinyo, M.L. Williams, and F.B.K. Kam, Analysis of the VENUS PWR Engineering Mockup Experiment — Phase I: Source Distribution, NUREG/CR-3888, ORNL/TM-9238, U.S. Nuclear Regulatory Commission, Washington, DC, (in press).
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© 1985 Springer Science+Business Media Dordrecht
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Williams, M.L., Morakinyo, P., Kam, F.B.K., Leenders, L., Minsart, G., Fabry, A. (1985). Calculation of the Neutron Source Distribution in the Venus PWR Mockup Experiment. In: Genthon, J.P., Röttger, H. (eds) Reactor Dosimetry. Springer, Dordrecht. https://doi.org/10.1007/978-94-010-9726-0_19
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DOI: https://doi.org/10.1007/978-94-010-9726-0_19
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