The VENUS-F Reactor for Nuclear Data Validation

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The VENUS-F Reactor for Nuclear Data Validation. / Krása, Antonin; Baeten, Peter; Fiorito, Luca; Kochetkov, Anatoly; Messaoudi, Nadia; Stankovskiy, Alexey; Van den Eynde, Gert; Vittiglio, Guido; Wagemans, Jan.

Reactor Dosimetry: 16th International Symposium: ASTM STP 1608. E10.05. ed. ASTM International, 2018. p. 286-295 STP160820170078.

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

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APA

Krása, A., Baeten, P., Fiorito, L., Kochetkov, A., Messaoudi, N., Stankovskiy, A., ... Wagemans, J. (2018). The VENUS-F Reactor for Nuclear Data Validation. In Reactor Dosimetry: 16th International Symposium: ASTM STP 1608 (E10.05 ed., pp. 286-295). [STP160820170078] ASTM International. https://doi.org/10.1520/STP160820170078

Vancouver

Krása A, Baeten P, Fiorito L, Kochetkov A, Messaoudi N, Stankovskiy A et al. The VENUS-F Reactor for Nuclear Data Validation. In Reactor Dosimetry: 16th International Symposium: ASTM STP 1608. E10.05 ed. ASTM International. 2018. p. 286-295. STP160820170078 https://doi.org/10.1520/STP160820170078

Bibtex - Download

@inproceedings{0b01a3a8039340ba875a1575d252f8c3,
title = "The VENUS-F Reactor for Nuclear Data Validation",
abstract = "Integral experiments for nuclear data validation have been carried out at the fast zero-power reactor VENUS-F at the Belgian Nuclear Research Centre SCKCEN since 2011. VENUS-F serves as a mock-up of MYRRHA, a fast, lead-bismuth cooled reactor/accelerator-driven system. First, solid lead was used as a coolant simulator and reflector at VENUS-F. In 2016, all lead in VENUS-F fuel assemblies was replaced by bismuth (in total, 625 kg), and a new experimental campaign was carried out with the aim of validating bismuth properties in integral experiments, mainly in the neutron energy region from 1 keV up to 10 MeV. Since 2017, lead and bismuth have been combined in fuel assemblies to simulate lead bismuth eutectic. An overview of the integral experiments is presented in this paper. Fission rate spatial distributions are compared with Monte Carlo calculations using various nuclear data libraries. The importance of accurate knowledge of material composition is discussed using high-purity bismuth samples (99.99 {\%}) as examples. These were characterized by neutron activation analysis at SCKCEN, mass spectrometry by the supplier (EVOCHEM), and neutron resonance capture analysis at the GELINA facility of the European Commission Joint Research Centre.",
keywords = "VENUS-F, MYRRHA, fast reactor, nuclear data, integral experiments, lead, bismuth, fission rate, neutron activation analysis, nductively coupled plasma mass spectrometry, neutron resonance capture analysis",
author = "Antonin Kr{\'a}sa and Peter Baeten and Luca Fiorito and Anatoly Kochetkov and Nadia Messaoudi and Alexey Stankovskiy and {Van den Eynde}, Gert and Guido Vittiglio and Jan Wagemans",
note = "Score=3",
year = "2018",
month = "11",
day = "19",
doi = "10.1520/STP160820170078",
language = "English",
pages = "286--295",
booktitle = "Reactor Dosimetry: 16th International Symposium",
publisher = "ASTM International",
edition = "E10.05",

}

RIS - Download

TY - GEN

T1 - The VENUS-F Reactor for Nuclear Data Validation

AU - Krása, Antonin

AU - Baeten, Peter

AU - Fiorito, Luca

AU - Kochetkov, Anatoly

AU - Messaoudi, Nadia

AU - Stankovskiy, Alexey

AU - Van den Eynde, Gert

AU - Vittiglio, Guido

AU - Wagemans, Jan

N1 - Score=3

PY - 2018/11/19

Y1 - 2018/11/19

N2 - Integral experiments for nuclear data validation have been carried out at the fast zero-power reactor VENUS-F at the Belgian Nuclear Research Centre SCKCEN since 2011. VENUS-F serves as a mock-up of MYRRHA, a fast, lead-bismuth cooled reactor/accelerator-driven system. First, solid lead was used as a coolant simulator and reflector at VENUS-F. In 2016, all lead in VENUS-F fuel assemblies was replaced by bismuth (in total, 625 kg), and a new experimental campaign was carried out with the aim of validating bismuth properties in integral experiments, mainly in the neutron energy region from 1 keV up to 10 MeV. Since 2017, lead and bismuth have been combined in fuel assemblies to simulate lead bismuth eutectic. An overview of the integral experiments is presented in this paper. Fission rate spatial distributions are compared with Monte Carlo calculations using various nuclear data libraries. The importance of accurate knowledge of material composition is discussed using high-purity bismuth samples (99.99 %) as examples. These were characterized by neutron activation analysis at SCKCEN, mass spectrometry by the supplier (EVOCHEM), and neutron resonance capture analysis at the GELINA facility of the European Commission Joint Research Centre.

AB - Integral experiments for nuclear data validation have been carried out at the fast zero-power reactor VENUS-F at the Belgian Nuclear Research Centre SCKCEN since 2011. VENUS-F serves as a mock-up of MYRRHA, a fast, lead-bismuth cooled reactor/accelerator-driven system. First, solid lead was used as a coolant simulator and reflector at VENUS-F. In 2016, all lead in VENUS-F fuel assemblies was replaced by bismuth (in total, 625 kg), and a new experimental campaign was carried out with the aim of validating bismuth properties in integral experiments, mainly in the neutron energy region from 1 keV up to 10 MeV. Since 2017, lead and bismuth have been combined in fuel assemblies to simulate lead bismuth eutectic. An overview of the integral experiments is presented in this paper. Fission rate spatial distributions are compared with Monte Carlo calculations using various nuclear data libraries. The importance of accurate knowledge of material composition is discussed using high-purity bismuth samples (99.99 %) as examples. These were characterized by neutron activation analysis at SCKCEN, mass spectrometry by the supplier (EVOCHEM), and neutron resonance capture analysis at the GELINA facility of the European Commission Joint Research Centre.

KW - VENUS-F

KW - MYRRHA

KW - fast reactor

KW - nuclear data

KW - integral experiments

KW - lead

KW - bismuth

KW - fission rate

KW - neutron activation analysis

KW - nductively coupled plasma mass spectrometry

KW - neutron resonance capture analysis

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/31726332

U2 - 10.1520/STP160820170078

DO - 10.1520/STP160820170078

M3 - In-proceedings paper

SP - 286

EP - 295

BT - Reactor Dosimetry: 16th International Symposium

PB - ASTM International

ER -

ID: 4756043