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Kochetkov A, Aït Abderrahim H, Baeten P, Krása A, Messaoudi N, Vittiglio G, Wagemans J. Integral experiments in the VENUS-F reactor. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108230] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Billebaud A, Lecouey JL, Chevret T, Chabod S, Doligez X, Kochetkov A, Krása A, Lecolley FR, Lehaut G, Marie N, Messaoudi N, Uyttenhove W, Vittiglio G, Wagemans J, Bécares V, Villamarin D, Mellier F. EXTENDED MSM METHOD TO ESTIMATE THE REACTIVITY OF A SUB-CRITICAL CORE DRIVEN BY AN ACCELERATOR BASED NEUTRON SOURCE. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124708005] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
The Modified Source Multiplication method is used to determine an unknown reactivity level of a reactor from a known one if one has access to the detector counting for both levels when the reactor is fed by a constant neutron source like an Am-Be source. When available, an accelerator driven source, in continuous mode, can be useful as its intensity can be tunable and then adapted to the experimental conditions. However, in that case, the MSM technique must be extended to account for an external source whose intensity, energy and angular distributions can vary from one measurement to another. In this paper, this Modified Multi-Source Multiplication (MMSM) method is applied to measurements done during the FREYA project in the GUINEVERE facility, operated with the GENEPI-3C accelerator providing a mixture of (D,T) and (D,D) neutrons. The monitoring of these sources through the detection of the associated charged particles allows the calculation of the MMSM factors and the estimate of the reactivity values. The results are compared in different configurations with the reactivity obtained with an Am-Be source or in dynamic measurements performed with GENEPI-3C. Their excellent agreement shows the possibility of using such accelerator-based neutron sources for MSM measurements when they are correctly monitored. This is of great interest for deep sub-critical level characterization for which detector count rates per source neutrons might be low.
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Krása A, Kochetkov A, Messaoudi N, Vittiglio G, Wagemans J. THE APPLICABILITY RANGE OF THE MODIFIED SOURCE MULTIPLICATION (MSM) METHOD TESTED IN THE FAST VENUS-F REACTOR. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124708001] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022] Open
Abstract
The MSM method is an experimental technique for determination of reactivity of a sub-critical reactor. It consists of one dynamic measurement followed by two static measurements, which use an extraneous neutron source. For the data analysis, the core averaged kinetic parameters need to be calculated as well as a spatially-dependent correction factor that corrects for the point kinetics approximation. In order to test the range for which the method is valid and to demonstrate the reliability of the correction factor calculations in a fast reactor, a dedicated experimental campaign was performed in the fast lead-bismuth VENUS-F reactor. The reactivity of a dozen of sub-critical configurations was measured with the MSM method using ten 235U fission chambers. The detectors were located at various distances from the active zone and from the extraneous neutron source, leading to a large range of values of a correction factor (calculated with the Monte Carlo MCNP5 code) used in the data analysis.
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Kochetkov A, Billebaud A, Chabod S, Krása A, Lecolley FR, Lecouey JL, Lehaut G, Marie N, Messaoudi N, Vittiglio G, Wagemans J. THE SOURCE JERK INTEGRALMETHOD FOR SUB-CRITICALITY MEASUREMENTS IN ADS. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124708002] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022] Open
Abstract
Three sub-critical (SC) core configurations were investigated in the VENUS-F zero power reactor coupled with the GENEPI-3C accelerator. The SC10 and SC12 were a mock-up of a MYRRHA start-up core and SC11 represented a more complex MYRRHA core loaded with various types of in-pile-sections. The sub-criticality of 11 variants of these VENUS-F cores was changed in several steps from -6$ down to -30$ using the safety and control rods. Their sub-criticalities were determined with the Source Jerk Integral (SJI) method using 11 fission chambers located all over the reactor. For the data analysis, the 8-group delayed neutron parameters from the JEFF-3.1.2 evaluated nuclear data library were used. Reliability and reproducibility of the experimental results were tested by repeating the measurements, swapping the detectors and varying the accelerator beam intensity, thus changing the detector count rates and verifying the validity of the dead time corrections. The obtained results are compared with MCNP calculations.
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Pyeon CH, Yamanaka M, Oizumi A, Fukushima M, Chiba G, Watanabe K, Endo T, Van Rooijen WG, Hashimoto K, Sakon A, Aizawa N, Kuriyama Y, Uesugi T, Ishi Y. First nuclear transmutation of 237Np and 241Am by accelerator-driven system at Kyoto University Critical Assembly. J NUCL SCI TECHNOL 2019. [DOI: 10.1080/00223131.2019.1618406] [Citation(s) in RCA: 11] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Affiliation(s)
- Cheol Ho Pyeon
- Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka, Japan
| | - Masao Yamanaka
- Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka, Japan
| | - Akito Oizumi
- Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Ibaraki, Japan
| | - Masahiro Fukushima
- Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Ibaraki, Japan
| | - Go Chiba
- Graduate School of Engineering, Hokkaido University, Sapporo, Japan
| | - Kenichi Watanabe
- Graduate School of Engineering, Nagoya University, Nagoya, Japan
| | - Tomohiro Endo
- Graduate School of Engineering, Nagoya University, Nagoya, Japan
| | | | - Kengo Hashimoto
- Atomic Energy Research Institute, Kindai University, Osaka, Japan
| | - Atsushi Sakon
- Atomic Energy Research Institute, Kindai University, Osaka, Japan
| | - Naoto Aizawa
- Graduate School of Engineering, Tohoku University, Sendai, Japan
| | - Yasutoshi Kuriyama
- Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka, Japan
| | - Tomonori Uesugi
- Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka, Japan
| | - Yoshihiro Ishi
- Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka, Japan
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Krása A, Kochetkov A, Messaoudi N, Stankovskiy A, Vittiglio G, Wagemans J. Impact of delayed neutron constants on reactivity effects measured in a fast reactor. EPJ WEB OF CONFERENCES 2019. [DOI: 10.1051/epjconf/201921103004] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022] Open
Abstract
Delayed neutron parameters of fast VENUS-F reactor core configurations are determined with Monte Carlo calculations using various nuclear data libraries. Differences in the calculated effective delayed neutron fraction and the impact of the delayed neutron data (6- or 8-group precursors) that are applied in the experimental data analysis on the measured reactivity effects are studied. Considerable differences are found due to application of 235U and 238U delayed neutron data from JEFF, JENDL and ENDF evaluations.
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Pyeon CH, Yamanaka M, Oizumi A, Fukushima M, Tsujimoto K. Experimental analyses of bismuth sample reactivity worth at Kyoto University Critical Assembly. J NUCL SCI TECHNOL 2018. [DOI: 10.1080/00223131.2018.1506368] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
Affiliation(s)
- Cheol Ho Pyeon
- Division of Nuclear Engineering Science, Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka, Japan
| | - Masao Yamanaka
- Division of Nuclear Engineering Science, Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka, Japan
| | - Akito Oizumi
- Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Ibaraki, Japan
| | - Masahiro Fukushima
- Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Ibaraki, Japan
| | - Kazufumi Tsujimoto
- Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Ibaraki, Japan
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Wagemans J, Borms L, Kochetkov A, Krása A, Van Grieken C, Vittiglio G. Nuclear instrumentation in VENUS-F. EPJ WEB OF CONFERENCES 2018. [DOI: 10.1051/epjconf/201817004027] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
VENUS-F is a fast zero power reactor with 30 wt% U fuel and Pb/Bi as a coolant simulator. Depending on the experimental configuration, various neutron spectra (fast, epithermal, and thermal islands) are present. This paper gives a review of the nuclear instrumentation that is applied for reactor control and in a large variety of physics experiments. Activation foils and fission chambers are used to measure spatial neutron flux profiles, spectrum indices, reactivity effects (with positive period and compensation method or the MSM method) and kinetic parameters (with the Rossi-alpha method). Fission chamber calibrations are performed in the standard irradiation fields of the BR1 reactor (prompt fission neutron spectrum and Maxwellian thermal neutron spectrum).
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Physics and technology for development of accelerator driven systems in India. PROGRESS IN NUCLEAR ENERGY 2017. [DOI: 10.1016/j.pnucene.2017.04.001] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Lecouey JL, Kochetkov A, Krása A, Baeten P, Bécares V, Billebaud A, Chabod S, Chevret T, Doligez X, Lecolley FR, Lehaut G, Marie N, Mellier F, Uyttenhove W, Villamarin D, Vittiglio G, Wagemans J. Monte Carlo MSM correction factors for control rod worth estimates in subcritical and near-critical fast neutron reactors. EPJ NUCLEAR SCIENCES & TECHNOLOGIES 2015. [DOI: 10.1051/epjn/e2015-50041-5] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
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