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Journal Articles

Non-destructive analysis of samples with a complex geometry by NRTA

Ma, F.; Kopecky, S.*; Alaerts, G.*; Harada, Hideo; Heyse, J.*; Kitatani, Fumito; Noguere, G.*; Paradela, C.*; $v{S}$alamon, L.*; Schillebeeckx, P.*; et al.

Journal of Analytical Atomic Spectrometry, 35(3), p.478 - 488, 2020/03

AA2019-0356.pdf:2.54MB

 Times Cited Count:4 Percentile:38.55(Chemistry, Analytical)

Journal Articles

Development of active neutron NDA system for nuclear materials

Toh, Yosuke; Ozu, Akira; Tsuchiya, Harufumi; Furutaka, Kazuyoshi; Kitatani, Fumito; Komeda, Masao; Maeda, Makoto; Koizumi, Mitsuo; Heyse, J.*; Paradela, C.*; et al.

Proceedings of INMM 59th Annual Meeting (Internet), 9 Pages, 2018/07

Journal Articles

Neutron resonance transmission analysis for measurement of nuclear materials in nuclear fuel

Tsuchiya, Harufumi; Kitatani, Fumito; Toh, Yosuke; Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*

Proceedings of INMM 59th Annual Meeting (Internet), 6 Pages, 2018/07

Journal Articles

CIELO collaboration summary results; International evaluations of neutron reactions on uranium, plutonium, iron, oxygen and hydrogen

Chadwick, M. B.*; Capote, R.*; Trkov, A.*; Herman, M. W.*; Brown, D. A.*; Hale, G. M.*; Kahler, A. C.*; Talou, P.*; Plompen, A. J.*; Schillebeeckx, P.*; et al.

Nuclear Data Sheets, 148, p.189 - 213, 2018/02

 Times Cited Count:67 Percentile:98.17(Physics, Nuclear)

The CIELO collaboration has studied neutron cross sections on nuclides that significantly impact criticality in nuclear facilities - $$^{235}$$U, $$^{238}$$U, $$^{239}$$Pu, $$^{56}$$Fe, $$^{16}$$O and $$^{1}$$H - with the aim of improving the accuracy of the data and resolving previous discrepancies in our understanding. This multi-laboratory pilot project, coordinated via the OECD/NEA Working Party on Evaluation Cooperation (WPEC) Subgroup 40 with support also from the IAEA, has motivated experimental and theoretical work and led to suites of new evaluated libraries that accurately reflect measured data and also perform well in integral simulations of criticality. This report summarizes our results and outlines plans for the next phase of this collaboration.

Journal Articles

Delayed $$gamma$$-ray spectroscopy combined with active neutron interrogation for nuclear security and safeguards

Koizumi, Mitsuo; Rossi, F.; Rodriguez, D.; Takamine, Jun; Seya, Michio; Bogucarska, T.*; Crochemore, J.-M.*; Varasano, G.*; Abbas, K.*; Pedersen, B.*; et al.

EPJ Web of Conferences, 146, p.09018_1 - 09018_4, 2017/09

 Times Cited Count:3 Percentile:85.84(Nuclear Science & Technology)

Journal Articles

Neutron resonance analysis for nuclear safeguards and security applications

Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*; Harada, Hideo; Kitatani, Fumito; Koizumi, Mitsuo; Tsuchiya, Harufumi

EPJ Web of Conferences, 146, p.09002_1 - 09002_4, 2017/09

 Times Cited Count:10 Percentile:98.13(Nuclear Science & Technology)

Journal Articles

Delayed gamma-ray analysis for characterization of fissile nuclear materials

Koizumi, Mitsuo; Rossi, F.; Rodriguez, D.; Takamine, Jun; Seya, Michio; Bogucarska, T.*; Crochemore, J.-M.*; Varasano, G.*; Abbas, K.*; Pedersen, B.*; et al.

EUR-28795-EN (Internet), p.868 - 872, 2017/00

Journal Articles

Development of active neutron NDA techniques for nuclear nonproliferation and nuclear security

Toh, Yosuke; Ozu, Akira; Tsuchiya, Harufumi; Furutaka, Kazuyoshi; Kitatani, Fumito; Komeda, Masao; Maeda, Makoto; Kureta, Masatoshi; Koizumi, Mitsuo; Seya, Michio; et al.

EUR-28795-EN (Internet), p.684 - 693, 2017/00

Journal Articles

LaBr$$_3$$ $$gamma$$-ray spectrometer for detecting $$^{10}$$B in debris of melted nuclear fuel

Koizumi, Mitsuo; Tsuchiya, Harufumi; Kitatani, Fumito; Harada, Hideo; Heyse, J.*; Kopecky, S.*; Mondelaers, W.*; Paradela, C.*; Schillebeeckx, P.*

Nuclear Instruments and Methods in Physics Research A, 837, p.153 - 160, 2016/11

 Times Cited Count:2 Percentile:19.46(Instruments & Instrumentation)

Journal Articles

Active neutron NDA techniques for nuclear non-proliferation applications, 4; Development of delayed gamma-ray spectroscopy; Experimental research plan

Koizumi, Mitsuo; Heyse, J.*; Mondelaers, W.*; Paradela, C.*; Pedersen, B.*; Schillebeeckx, P.*; Seya, Michio; Rodriguez, D.; Takamine, Jun

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 6 Pages, 2015/12

The fission-product yield distributions are unique for each fissionable nuclide and interrogating neutron energy. Ratios of fissile materials (e.g. $$^{235}$$U, $$^{239}$$Pu, and $$^{241}$$Pu), therefore, could be deduced from differences in the observed neutron-induced Delayed Gamma-ray (DG) spectra characterized by the difference of these yields. This DG Spectroscopy (DGS) project includes research and development of a measurement system along with confirming and improving nuclear data. Experiments will be held at multiple facilities, including ITU/Ispra (Italy), IRMM/Geel (Belgium), and KURRI/Kumatori (Japan), using a wide range of neutron sources and nuclear material sample targets. The experimental efforts of this DGS project are described in this presentation.

Journal Articles

Characteristics of neutron resonance densitometry, 1; Neutron resonance transmission analysis

Kitatani, Fumito; Harada, Hideo; Koizumi, Mitsuo; Tsuchiya, Harufumi; Kureta, Masatoshi; Becker, B.*; Kopecky, S.*; Heyse, J.*; Paradela, C.*; Mondelaers, W.*; et al.

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/12

From 2012 to 2014, Neutron Resonance Densitometry (NRD) is being developed as a non-destructive assay to quantify U and Pu isotopes. NRD is composed of neutron resonance transmission analysis (NRTA) and Neutron Resonance Capture Analysis (NRCA)/Prompt Gamma-ray Analysis (PGA). NRTA in NRD plays a role of quantifying the amounts of the isotopes of a nuclear fuel material (U, Pu) in molten fuel debris. Therefore, the neutron absorption measurement using Time-of-Flight (TOF) method is carried out. A demonstration NRTA experiment was performed at a neutron time of flight facility GELINA (Belgium). Consequently, we succeeded in iquantifying the randomly selected sample from Au, W, Rh, Nb, Cu. Co, Mn, B contained in a black box. In this presentation, we describe the principle of measurement of the developed NRTA and explain details of the demonstration experiment.

Journal Articles

Characteristics of neutron resonance densitometry, 2; Neutron resonance capture analysis

Tsuchiya, Harufumi; Harada, Hideo; Koizumi, Mitsuo; Kitatani, Fumito; Kureta, Masatoshi; Becker, B.*; Kopecky, S.*; Heyse, J.*; Paradela, C.*; Mondelaers, W.*; et al.

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/12

Neutron Resonance Densitometry (NRD) was developed as a non-destructive assay to quantify U and Pu isotopes in particle-like debris. NRD is composed of neutron resonance transmission analysis (NRTA) and Neutron Resonance Capture Analysis (NRCA) or Prompt Gamma-ray Analysis (PGA). NRCA/PGA in NRD plays a role of identifying impurities in debris under the high-radiation field primarily caused by $$^{137}$$Cs. For this purpose, a novel LaBr$$_3$$ $$gamma$$-ray detector employing specific shields has been newly developed. With the developed $$gamma$$-ray detector, a demonstration NRCA experiment was performed at a neutron time of flight facility GELINA (Belgium). As a result, samples (Hf, Gd, Ni) placed in a black box that is completely sealed by third party were successfully identified by the experiment. This presentation explains the design concept of the $$gamma$$ ray detector including its detection principle and details of the demonstration NRCA experiment.

Journal Articles

Techniques of neutron resonance capture analysis and prompt $$gamma$$-ray analysis for active neutron NDA

Koizumi, Mitsuo; Tsuchiya, Harufumi; Kitatani, Fumito; Kureta, Masatoshi; Seya, Michio; Harada, Hideo; Heyse, J.*; Kopecky, S.*; Mondelaers, W.*; Paradela, C.*; et al.

Proceedings of 37th ESARDA Annual Meeting (Internet), p.852 - 858, 2015/08

Journal Articles

Technique of neutron resonance transmission analysis for active neutron NDA

Tsuchiya, Harufumi; Koizumi, Mitsuo; Kitatani, Fumito; Kureta, Masatoshi; Harada, Hideo; Seya, Michio; Heyse, J.*; Kopecky, S.*; Mondelaers, W.*; Paradela, C.*; et al.

Proceedings of 37th ESARDA Annual Meeting (Internet), p.846 - 851, 2015/08

One of non-destructive techniques using neutron resonance reaction is neutron resonance transmission analysis (NRTA). We are presently developing a new active neutron non-destructive method including NRTA in order to detect and quantify special nuclear materials (SNMs) in nuclear fuels containing MA. We aim at applying the technique to not only particle-like debris but also other materials in high radiation field. For this aim, we make use of fruitful knowledge of neutron resonance densitometry (NRD) that was developed for particle-like debris in melted fuel. NRTA detects and quantifies SNMs by means of analyzing a neutron transmission spectrum via a resonance shape analysis. In this presentation, we explain the basic of NRTA and its role in the active neutron technique. Then, with knowledge obtained in the development of NRD, we discuss items to be investigated for NRTA in our active neutron technique.

Journal Articles

NRD demonstration experiments at GELINA

Paradela, C.*; Alaerts, G.*; Becker, B.*; Harada, Hideo; Heyse, J.*; Kitatani, Fumito; Koizumi, Mitsuo; Kopecky, S.*; Mondelaers, W.*; Moens, A.*; et al.

EUR-27507-EN, 16 Pages, 2015/04

Journal Articles

Measurement of the neutron capture cross section of the $$s$$-only isotope $$^{204}$$Pb from 1 eV to 440 keV

Domingo-Pardo, C.*; Abbondanno, U.*; Aerts, G.*; $'A$lvarez, H.*; Alvarez-Velarde, F.*; Andriamonje, S.*; Andrzejewski, J.*; Assimakopoulos, P.*; Audouin, L.*; Badurek, G.*; et al.

Physical Review C, 75(1), p.015806_1 - 015806_9, 2007/01

 Times Cited Count:34 Percentile:86.88(Physics, Nuclear)

The neutron capture cross section of $$^{204}$$Pb has been measured at the CERN n_TOF installation with high resolution in the energy range from 1 eV to 440 keV. In the interval between 100 keV and 440 keV we report the average cross section. The background in the entire energy range was reliably determined from the measurement of a $$^{208}$$Pb sample. We obtain a Maxwellian average capture cross section for $$^{204}$$Pb at $$kT$$ = 30 keV of 79(3) mb, in agreement with previous experiments. However our cross section at $$kT$$ = 5 keV is about 35 % larger than the values reported so far. The implications of the new cross section for the $$s$$-process abundance contributions in the Pb/Bi region are discussed.

Journal Articles

Resonance capture cross section of $$^{207}$$Pb

Domingo-Pardo, C.*; Abbondanno, U.*; Aerts, G.*; $'A$lvarez, H.*; Alvarez-Velarde, F.*; Andriamonje, S.*; Andrzejewski, J.*; Assimakopoulos, P.*; Audouin, L.*; Badurek, G.*; et al.

Physical Review C, 74(5), p.055802_1 - 055802_6, 2006/11

 Times Cited Count:27 Percentile:81.23(Physics, Nuclear)

The radiative neutron capture cross section of $$^{207}$$Pb has been measured at the CERN n_TOF facility using the pulse height weighting technique in the resoleved region. The measurement has been performed with an optimized setup of two $$C_{6}D_{6}$$ scintillation detectors, which allowed us to reduce scattered neutron backgrounds down to a negligible level. Resonance parameters have been determined for 16 resonances by means of an R-matrix analysis in the neutron energy range from 3 keV to 320 keV. Good agreement with previous measurements was found at low neutron energies, whereas substantial discrepancies appear beyond 45 keV. With the present results, we obtain an s-process contribution of 77$$pm$$8 % to the solar abundance of $$^{207}$$Pb.

Journal Articles

New measurement of neutron capture resonances in $$^{209}$$Bi

Domingo-Pardo, C.*; Abbondanno, U.*; Aerts, G.*; $'A$lvarez, H.*; Alvarez-Velarde, F.*; Andriamonje, S.*; Andrzejewski, J.*; Assimakopoulos, P.*; Audouin, L.*; Badurek, G.*; et al.

Physical Review C, 74(2), p.025807_1 - 025807_10, 2006/08

 Times Cited Count:47 Percentile:90.35(Physics, Nuclear)

The neutron capture cross section of $$^{209}$$Bi has been measured at the CERN n_TOF facility by employing the pulse-height-weighting technique. Improvements over previous measurements are mainly because of an optimized detection system, which led to a practically negligible neutron sensitivity. Because $$^{209}$$Bi is the last stable isotope in the reaction path of the stellar s-process, the Maxwellian averaged capture cross section is important for the recycling of the reaction flow by alpha decays. In the relevant stellar range of thermal energies between $$kT$$ = 5 and 8 keV our new capture rate is about 16% higher than the presently accepted value used for nucleosynthesis calculations. The present cross section measurement is also of relevance for the design of accelerator driven systems based on a liquid metal Pb/Bi spallation target.

Journal Articles

Neutron capture cross section of $$^{232}$$Th measured at the n_TOF facility at CERN in the unresolved resonance region up to 1 MeV

Aerts, G.*; Abbondanno, U.*; $'A$lvarez, H.*; Alvarez-Velarde, F.*; Andriamonje, S.*; Andrzejewski, J.*; Assimakopoulos, P.*; Audouin, L.*; Badurek, G.*; Baumann, P.*; et al.

Physical Review C, 73(5), p.054610_1 - 054610_10, 2006/05

We have measured the neutron capture reaction yield of $$^{232}$$Th at the neutron tim-of-flight facility n_TOF at CERN in the energy range from 1 eV to 1 MeV. The average capture cross section has been extracted in the energy range from 4 keV up to 1 MeV with an overall accuracy better than 4 %. An independent IAEA evaluation shows good agreement with the data.

Journal Articles

Neutron capture cross section of $$^{232}$$Th measured at the n_TOF facility at CERN in the unresolved resonance region up to 1 MeV

Aerts, G.*; Abbondanno, U.*; $'A$lvarez, H.*; Alvarez-Velarde, F.*; Andriamonje, S.*; Andrzejewski, J.*; Assimakopoulos, P.*; Audouin, L.*; Badurek, G.*; Baumann, P.*; et al.

Physical Review C, 73(5), p.054610_1 - 054610_10, 2006/05

 Times Cited Count:45 Percentile:89.74(Physics, Nuclear)

We have measured the neutron capture reaction yield of $$^{232}$$Th at the neutron time-of-flight facility n_TOF at CERN in the energy range from 1 eV to 1 MeV. The average capture cross section has been extracted in the energy range from 4 keV up to 1 MeV with an overall accuracy better than 4%. An independent IAEA evaluation shows good agreement with the data.

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