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Journal Articles

The Joint evaluated fission and fusion nuclear data library, JEFF-3.3

Plompen, A. J. M.*; Cabellos, O.*; De Saint Jean, C.*; Fleming, M.*; Algora, A.*; Angelone, M.*; Archier, P.*; Bauge, E.*; Bersillon, O.*; Blokhin, A.*; et al.

European Physical Journal A, 56(7), p.181_1 - 181_108, 2020/07

 Times Cited Count:234 Percentile:99.41(Physics, Nuclear)

The Joint Evaluated Fission and Fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides $$^{235}$$U, $$^{238}$$U and $$^{239}$$Pu, on $$^{241}$$Am and $$^{23}$$Na, $$^{59}$$Ni, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yileds, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 is excellent for a wide range of nuclear technology applications, in particular nuclear energy.

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:61 Percentile:98.12(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

The CIELO collaboration; Progress in international evaluations of neutron reactions on Oxygen, Iron, Uranium and Plutonium

Chadwick, M. B.*; Capote, R.*; Trkov, A.*; Kahler, A. C.*; Herman, M. W.*; Brown, D. A.*; Hale, G. M.*; Pigni, M.*; Dunn, M.*; Leal, L.*; et al.

EPJ Web of Conferences, 146, p.02001_1 - 02001_9, 2017/09

 Times Cited Count:6 Percentile:95.25

The CIELO collaboration has studied neutron cross sections on nuclides ($$^{16}$$O, $$^{56}$$Fe, $$^{235,238}$$U and $$^{239}$$Pu) that significantly impact criticality in nuclear technologies 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.

Journal Articles

The CIELO Collaboration; Neutron reactions on $$^1$$H, $$^{16}$$O, $$^{56}$$Fe, $$^{235,238}$$U, and $$^{239}$$Pu

Chadwick, M. B.*; Dupont, E.*; Bauge, E.*; Blokhin, A.*; Bouland, O.*; Brown, D. A.*; Capote, R.*; Carlson, A. D.*; Danon, Y.*; De Saint Jean, C.*; et al.

Nuclear Data Sheets, 118, p.1 - 25, 2014/04

 Times Cited Count:105 Percentile:98.52(Physics, Nuclear)

CIELO (Collaborative International Evaluated Library Organization) provides a new working paradigm to facilitate evaluated nuclear reaction data advances. It brings together experts from across the international nuclear reaction data community to identify and document discrepancies among existing evaluated data libraries, measured data, and model calculation interpretations, and aims to make progress in reconciling these discrepancies to create more accurate ENDF-formatted files. The focus will initially be on a small number of the highest-priority isotopes, namely $$^{1}$$H, $$^{16}$$O, $$^{56}$$Fe, $$^{235,238}$$U, and $$^{239}$$Pu. This paper identifies discrepancies between various evaluations of the highest priority isotopes. The evaluated data for these materials in the existing nuclear data libraries are reviewed, and some integral properties are given. The paper summarizes a program of nuclear science and computational work needed to create the new CIELO nuclear data evaluations.

Journal Articles

Neutronics experiments on HCPB and HCLL TBM mock-ups in preparation of nuclear measurements in ITER

Batistoni, P.*; Angelone, M.*; Carconi, P.*; Fischer, U.*; Fleischer, K.*; Kondo, Keitaro; Klix, A.*; Kodeli, I.*; Leichtle, D.*; Petrizzi, L.*; et al.

Fusion Engineering and Design, 85(7-9), p.1675 - 1680, 2010/12

 Times Cited Count:31 Percentile:88.74(Nuclear Science & Technology)

The EU is developing two test blanket modules (TBM), the Helium Cooled Pebble Bed (HCPB) and the Helium Cooled Lithium Lead (HCLL), which will be tested in ITER. Here neutronics experiments with a mockup for HCLL TBM were carried out. Detail distributions of the tritium production rate inside the mockup were measured with various methods. A lithium diamond detector developed as a neutron monitor for fusion devices has also been used as a tritium detector. Activation reaction rates inside the mockup were also measured. These measured data agreed with calculation results buy using MCNP and FENDL-2.1 within 10%, which demonstrated that the prediction accuracy was high. Sensitivity and uncertainty analyses suggested that the uncertainty of the tritium production rate from the nuclear data uncertainty was small, usually below 2%.

Journal Articles

Use of CAD generated geometry data in Monte Carlo transport calculations for ITER

Fischer, U.*; Iida, Hiromasa; Li, Y.*; Loughlin, M.*; Sato, Satoshi; Serikov, A.*; Tsige-Tamirat, H.*; Tautges, T.*; Wilson, P. P.*; Wu, Y.*

Fusion Science and Technology, 56(2), p.702 - 709, 2009/08

 Times Cited Count:12 Percentile:62.42(Nuclear Science & Technology)

Several approaches have been recently developed to make available CAD geometry data for Monte Carlo calculations with the MCNP code. Among these are conversion tools for the automatic generation of geometry models in MCNP representation such as MCAM of China, McCad of Germany, and GEOMIT of JAEA, as well as the direct DAG-MCNPX approach developed by USA. An extensive benchmark exercise has been conducted on ITER between 2005 and 2007 with the objective to test and validate the different approaches and thereby check the maturity level for ITER design applications. The exercise encompassed the generation of a dedicated neutronics CATIA model based on available engineering CAD design data, the conversion into MCNP geometry, the verification of the converted models, and a number of calculations to compare the different approaches with regard to the performance and the validity of the results obtained. The paper briefly reviews the different approaches and provides a detailed description of the ITER benchmark effort, its results and conclusions. As a key issue, the recommendations are discussed that need to be followed when generating a neutronics CAD model for ITER design calculations. This is considered essential since the ITER quality assurance requirements will request the consistency of the analysis models and the underlying engineering CAD models.

Journal Articles

ITER nuclear analysis strategy and requirements

Loughlin, M. J.*; Batistoni, P.*; Konno, Chikara; Fischer, U.*; Iida, Hiromasa; Petrizzi, L.*; Polunovskiy, E.*; Sawan, M.*; Wilson, P.*; Wu, Y.*

Fusion Science and Technology, 56(2), p.566 - 572, 2009/08

 Times Cited Count:40 Percentile:92.61(Nuclear Science & Technology)

It is envisaged that ITER should produce as much as 700 MW of fusion power. This equates to the production of 2.48$$times$$10$$^{20}$$ 14MeV neutrons/s which will give an uncollided flux at the first wall of approximately 4$$times$$10$$^{13}$$ n/cm$$^{2}$$/s and a total with the addition of the collided to some 10$$^{14}$$ n/cm$$^{2}$$/s. ITER is therefore a significant nuclear facility and it is essential that an efficient and coherent strategy for nuclear analysis is in place. This paper reviews the status of the methods applied to date and recommends the future strategy which ITER should adopt to address the continuing requirements and responsibilities. This is done by consideration of the application of radiation transport codes, the creation of suitable models, developments in information technology, and the management tools which will be required. Areas in which new codes and techniques need to be developed will be identified.

Journal Articles

No evidence for DNA and early cytogenetic damage in bystander cells after heavy-ion microirradiation at two facilities

Fournier, C.*; Barberet, P.*; Pouthier, T.*; Ritter, S.*; Fischer, B.*; Voss, K.-O.*; Funayama, Tomoo; Hamada, Nobuyuki*; Kobayashi, Yasuhiko; Taucher-Scholz, G.*

Radiation Research, 171(5), p.530 - 540, 2009/05

 Times Cited Count:43 Percentile:77.1(Biology)

Journal Articles

Development needs of nuclear data for fusion technology

Fischer, U.*; Batistoni, P.*; Forrest, R. A.*; Konno, Chikara; Perel, R. L.*; Seidel, K.*; Simakov, S. P.*

Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.973 - 978, 2008/05

An overview is presented of the nuclear data required for nuclear design analyses of fusion technology focusing on ITER, the International Thermonuclear Experimental Reactor, and IFMIF, the International Fusion Materials Irradiation Facility. The status of the available data evaluations and libraries is reviewed with regard to the required materials/nuclides and data types and, in particular, with regard to their quality as compared to differential and integral experimental data. Future development needs are identified on this basis addressing nuclear data evaluations for neutron and photon transport simulations, cross-section data for activation and transmutation calculations, and co-variance data for uncertainty analyses.

Journal Articles

Neutronics experiment on a helium cooled pebble bed (HCPB) breeder blanket mock-up

Batistoni, P.*; Angelone, M.*; Bettinali, L.*; Carconi, P.*; Fischer, U.*; Kodeli, I.*; Leichtle, D.*; Ochiai, Kentaro; Perel, R.*; Pillon, M.*; et al.

Fusion Engineering and Design, 82(15-24), p.2095 - 2104, 2007/10

 Times Cited Count:25 Percentile:83.37(Nuclear Science & Technology)

A neutronics experiment has been performed in the frame of European Fusion Technology Program on a mock-up of the EU Test Blanket Module (TBM), Helium Cooled Pebble Bed (HCPB) concept, with the objective to validate the capability of nuclear data to predict nuclear responses, such as the tritium production rate (TPR), with qualified uncertainties. In the experiment, the TPR has been measured using Li$$_{2}$$CO$$_{3}$$ pellets at various depths at two symmetrical positions at each depth, one in the upper and one in the lower breeder cassette. Three independent measurements were performed by ENEA, TUD/VKTA and JAEA. The neutron flux in the beryllium layer was measured as well using activation foils.

Journal Articles

Estimation of radioactivities in the IFMIF liquid lithium loop due to the erosion and corrosion of target back-wall

Yamauchi, Michinori*; Takemura, Morio*; Nakamura, Hiroo; Fischer, U.*; Ida, Mizuho*; Mori, Seiji*; Sato, Satoshi; Nishitani, Takeo; Simakov, S. P.*; Sugimoto, Masayoshi

Fusion Science and Technology, 47(4), p.1008 - 1011, 2005/05

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

SIMMER-III: A Computer Program for LMFR Core Disruptive Accident Analysis; Version 3.A Model Summary and Program Description

Yamano, Hidemasa; Fujita, Satoshi; Tobita, Yoshiharu; Kamiyama, Kenji; Kondo, Satoru; Morita, Koji*; Fischer, E. A.; Brear, D. J.; Shirakawa, Noriyuki*; Cao, X.; et al.

JNC TN9400 2003-071, 340 Pages, 2003/08

JNC-TN9400-2003-071.pdf:1.54MB

An advanced safety analysis computer code, SIMMER-III, has been developed to investigate postulated core disruptive accidents in liquid-metal fast reactors (LMFRs). SIMMER-III is a two-dimensional, three-velocity-field, multiphase, multicomponent, Eulerian, fluid-dynamics code coupled with a space-dependent neutron kinetics model. By completing and integrating all the physical models originally intended at the beginning of this code development project, SIMMER-III is now applicable to integral reactor calculations and other complex multiphase flow problems. A systematic code assessment program, conducted in collaboration with European research organizations, has shown that the advanced features of the code have resolved many of the limitations and problem areas in the previous SIMMER-II code. In this report, the models, numerical algorithms and code features of SIMMER-III Version 3.A are described along with detailed program description. Areas which require future model refinement are also discussed. SIMMER-III Version 3.A, a coupled fluid-dynamics and neutronics code system, is expected to significantly improve the flexibility and reliability of LMFR safety analyses.

Journal Articles

Commensurate-incommensurate magnetic phase transitions of CePtAl

D$"o$nni, A.*; Kitazawa, Hideaki*; Fischer, P.*; Tang, J.*; Kogi, M.*; Endo, Yasuo*; Morii, Yukio

Journal of Physics; Condensed Matter, 7, p.1663 - 1678, 1995/00

 Times Cited Count:32 Percentile:83.49(Physics, Condensed Matter)

no abstracts in English

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