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Journal Articles

Journal Articles

Achievements on oxide and nitride ADS fuels within the European project; EUROTRANS

Delage, F.*; Arai, Yasuo; Belin, R.*; Chen, X.*; D'Agata, E.*; Hania, R.*; Klaassen, F.*; Maschek, W.*; Oigawa, Hiroyuki; Ottaviani, J. P.*; et al.

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 8 Pages, 2011/12

The European FP-6 integrated project EUROTRANS was devoted to management of high-level wastes from nuclear power plants, focusing on MA transmutation in ADS. The object of the project was the assessment of the design and feasibility of an industrial ADS prototype dedicated to MA transmutation. JAEA joined in the project as one of partners. This paper summarizes the ADS fuel development carried out in this project. As for the oxide fuel, a primary candidate, the results of design study, performance in normal operation, safety analysis, irradiation tests and out-of-pile property measurements are described. As for the nitride fuel, an alternative of oxide fuel, the results of irradiation tests and out-of-pile property measurements, and the progress of pyrochemical process for spent fuel treatment are described.

Journal Articles

First 3-D calculation of core disruptive accident in a large-scale sodium-cooled fast reactor

Yamano, Hidemasa; Tobita, Yoshiharu; Fujita, Satoshi; Maschek, W.*

Annals of Nuclear Energy, 36(3), p.337 - 343, 2009/04

 Times Cited Count:16 Percentile:71.14(Nuclear Science & Technology)

The SIMMER-IV computer code is a three-dimensional fluid-dynamics code coupled with a fuel-pin model and a space- and energy-dependent neutron transport kinetics model. The present study attempted the first application of SIMMER-IV to a core disruptive accident in a large-scale sodium-cooled fast reactor. A main point of this study was to investigate reactivity effects with fuel relocation under three-dimensional core representation including control rods. The calculation has indicated that the fuel discharge from the core was disturbed by a significant flow resistance at the entrance nozzle in the current design. Additional static neutronic calculations have been performed to compare basic neutronic characteristics between different scale cores. The static neutronic calculations have clarified that the outward fuel compaction within the inner core increased the reactivity in the large-scale core unlike the small-scale core.

Journal Articles

First 3-D calculation of core disruptive accident in a large scale sodium-cooled fast reactor

Yamano, Hidemasa; Tobita, Yoshiharu; Fujita, Satoshi; Maschek, W.*

Proceedings of International Conference on the Physics of Reactors, Nuclear Power; A Sustainable Resource (PHYSOR 2008) (CD-ROM), 8 Pages, 2008/09

The present study attempted the first application of SIMMER-IV to a CDA in a large-scale SFR to draw event progression and to grasp key characteristics. Since the 3-D calculation requires much computation time, the SIMMER-IV calculation focused on the early stage of the transition phase in this study. The calculation result indicated mild event progression without recriticality. Compared to a small-scale SFR, it was found that the radial sloshing reactivity was not so significant in a large-scale SFR.

Journal Articles

SIMMER-III; A Coupled neutronics-thermohydraulics computer code for safety analysis

Yamano, Hidemasa; Tobita, Yoshiharu; Fujita, Satoshi; Suzuki, Toru; Kamiyama, Kenji; Morita, Koji*; Maschek, W.*; Pigny, S.*

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 8 Pages, 2007/04

To simulate complex phenomena during core disruptive accidents in sodium-cooled fast reactors, JAEA has been developing the SIMMER-III code,which is two-dimensional, multi-velocity-field, multi-phase, multi-component, Eulerian, fluid-dynamics code coupled with a fuel-pin model and a space- and energy-dependent neutron kinetics model. Recently, the three-dimensional code SIMMER-IV is also developed with the same physical model as SIMMER-III. In the present paper, the models and methods of SIMMER-III/IV are briefly reviewed with highlighting the recent improvements. The major achievements of the code assessment program are then described, followed by presentation of practical applications. A three-dimensional calculation with SIMMER-IV are also shown to indicate more realistic accident scenario. In addition, this calculation result show the disrupted core state for investigating the post-accident material relocation and heat removal phase.

Journal Articles

The Development of SIMMER-III, an advanced computer program for LMFR safety analysis, and its application to sodium experiments

Tobita, Yoshiharu; Kondo, Satoru; Yamano, Hidemasa; Morita, Koji*; Maschek, W.*; Coste, P.*; Cadiou, T.*

Nuclear Technology, 153(3), p.245 - 255, 2006/03

 Times Cited Count:71 Percentile:97.54(Nuclear Science & Technology)

SIMMER-III is a general two-dimensional, three-velocity-field, multiphase, multicomponent, Eulerian, fluid-dynamics code coupled with a space-time and energy-dependent neutron transport kinetics model. The philosophy behind the SIMMER development was to generate a versatile and flexible tool, applicable for the safety analysis of various reactor types with different neutron spectra and coolants, up the new accelerator driven systems (ADS) for waste transmutation. SIMMER-III has proven especially well suited for fast spectrum systems as the LMFR, where it is one of the key codes for safety analysis, including its application within licensing procedures. To serve especially the last purpose, the code must be made sufficiently robust and reliable, and be tested and validated extensively. A comprehensive and systematic assessment program of the code has been conducted. This paper gives the major achievement of this assessment program. The code assessment program is an ongoing effort. Two major milestones have been achieved in the past by completing two assessment campaigns, Phase 1 and Phase 2. Phase 1 for fundamental code assessment of individual models; and Phase 2 for integral code assessment for key phenomena relevant to LMFR safety. Through this systematic code assessment program, comprehensive validation of the physical models has been conducted step-by-step. The assessment program has demonstrated that SIMMER-III is a state-of-the-art code with advanced models sufficiently flexible for simulating transient multiphase phenomena occurring during CDAs. In this paper we will concentrate on the specifics of the code, mainly reflected at its application to sodium experiments related to the safety of LMFR.

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.

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