MA/LLFP Transmutation Experiment Options in the Future Monju Core
|
|
- Preston Weaver
- 5 years ago
- Views:
Transcription
1 MA/LLFP Transmutation Experiment Options in the Future Monju Core Akihiro KITANO 1, Hiroshi NISHI 1*, Junichi ISHIBASHI 1 and Mitsuaki YAMAOKA 2 1 International Cooperation and Technology Development Center, Japan Nuclear Cycle Development Institute, Tsuruga, Fukui, , Japan 2 Power and Industrial Systems Research and Development Center, Toshiba Co., Kawasaki, Kanagawa, , Japan Future experimental irradiation test options for the minor actinide (MA) and long-lived fission product (LLFP) transmutation in Monju core have been studied to search for and to demonstrate the possible contribution of Monju to the future commercialization of FBR technology. It was shown that MA incineration rate for 148 EFPDs by 5 cycles operation was evaluated to be 26% to 32% for the core region loading case and 13% for the radial blanket region loading case. As regards LLFP irradiation test, the transmutation rate was evaluated to be 0.7%/year for without-moderator case and 1.2%/year to 1.4%/year for with-moderator case. These results showed the capability of Monju core for profitable experimental data acquisition, without any significant disturbance on the core characteristics with some slight design modifications. KEYWORDS: fast reactors, minor actinides, long-lived fission products, irradiation experiment, transmutation I. Introduction Deposit of high-level radioactive wastes (HLW) is indispensable to nuclear fuel cycle. Reduction of environmental burden can be achieved by reducing the radioactive hazard of the minor actinides (MAs: Np, Am, Cm) and the long-lived fission products (LLFPs: 99 Tc, 129 I, 135 Cs and so on), contained in the HLW as a result of nuclear power generation. It was known that the radioactive hazard of the HLW would be decreased to that of the original natural uranium ore after several hundreds years assuming that all the MAs and LLFPs are separated from the HLW and transmuted into short-lived radioactive nuclides or stable nuclides in the nuclear reactors. Transmutation of MA/LLFP can be efficiently and effectively achieved by the fast neutron spectrum system because of its high neutron flux level and its neutron surplus available for transmutation when compared with the thermal or other spectrum systems. Much larger fission-to-capture cross-section ratio of MAs in the fast spectrum system substantially makes it as the almost only effective way of MA transmutation 1-4). Negligibly small contribution of thermal neutrons in the active core region in the fast spectrum system also enables effective MA transmutation, especially with large amount of core loading. Fast reactors can offer wider range of neutron spectrum and higher level of neutron flux than that of LWRs. In the MA/LLFP separation and transmutation studies, fast reactor has been and still is considered to be one of the most feasible and promising candidates 5). MA/LLFP transmutation experiment options in the future Monju core are to be proposed based on the above mentioned fundamental considerations in this study. * Corresponding author, Tel , FAX , nishi@t-hq.jnc.go.jp are to be proposed based on the above mentioned fundamental considerations in this study. Investigation of the MA transmutation experiment has been performed based on the preceding studies in this field. Reactor design studies on MA transmutation in FBR cores have revealed that it reduces burn-up reactivity swing while increasing the sodium void reactivity and reducing the Doppler coefficient, which needs some safety considerations. Because of these safety considerations the maximum ratio of MA mixture in the core fuel is said to be limited below 5% and to be allowed up to 10% with some penalty on core characteristics. Taking into account the influence of the MA-mixed test fuel assembly loading on the core characteristics, both the nine test assemblies loaded in the core region case and the eighteen assemblies loaded in the radial blanket region case were studied. And the radial blanket region loading case was evaluated to be preferable to avoid any significant disturbance on the core characteristics. As regards LLFP transmutation, 99 Tc was selected as the typical target nuclide to be irradiated 6) because of its large neutron absorption cross section, chemically inert form in the reactor core as a metal and no need for isotopic separation. LLFP loading affects the core characteristics as well as MA loading. Fifty-four test assemblies, at the maximum, loaded in the radial blanket region case was studied. Zirconium-hydride (ZrH 1.7 ; The hydrogen ratio is an assumed value) was partially loaded in the test assembly as the neutron spectrum moderator. This maximum number of assemblies was assumed in order to evaluate the allowable number of loaded assemblies. The results showed the capability of Monju core for profitable experimental data acquisition, without any significant disturbance on the core characteristics.
2 Monju reference core layout Core layout for MA transmutation experiment (Homogeneous loading type) Core layout for MA transmutation experiment (Heterogeneous loading type) Core layout for LLFP transmutation experiment Inner core fuel assembly Outer core fuel assembly Radial blanket fuel assembly Control rod (Primary) Control rod (Back up) Irradiation test rig (MA) Irradiation test rig (LLFP) Neutron source assembly Fig. 1 Core layout of Monju
3 II. Prototype Fast Breeder Reactor Monju Experimental irradiation of MA/LLFP transmutation was assumed in the future Monju core in this study. Monju is the prototype fast breeder reactor in our country with an electric power of 280MWe (714MWt), a sodium-cooled loop-type reactor. The Monju core consists of 715 assemblies (198 core fuel assemblies, 172 radial blanket fuel assemblies, 19 control rod assemblies, etc.) and is fueled with UO 2 -PuO 2 mixed oxide fuel. The core layout of Monju is shown in Fig. 1 and the fundamental core specifications are shown in Table 1. Figure 2 shows the side view of Monju core. Monju has been shut down since December 8, 1995 when the sodium leak accident occurred in the secondary heat transport system. The Role of Monju was clearly redefined in the "Long-Term Program for Research, Development and Utilization of Nuclear Energy, revised by Atomic Energy Commission in November 2000, after the accident. Monju can be considered as one of the assets of the humankind, which can demonstrate the prominent FBR characteristics in the nearly commercialized scale. The confirmation of the fundamental performances, such as breeding ratio, etc. has been and continues to be its mission. This is essential for the prototype reactor. Monju should be restarted at the earliest stage possible, and the sodium handling technology should be established for that purpose. The demonstration of the reliability as a power station should be pursued simultaneously. The earliest demonstration of the world s most advanced technology will be the next mission. Adjustment of the plutonium stockpile and incineration of trans-uranics, etc., are to be demonstrated as pursued in the Feasibility Study on Commercialization of FBR Cycle Technology, conducted by JNC. The possibility of Monju, to contribute to the future commercialization of FBR technology, should be pursued and demonstrated. Accordingly, the irradiation experiments of Fig Upper Axial Blanket Inner Core Outer Core Lower Axial Blanket Radial Blanket Monju core side view Unit : mm MA/LLFP transmutation are to be performed just after the confirmation of the current core characteristics. III. Analytical Calculations and Results MA and LLFP transmutation irradiation experiments were studied individually because the disturbances, to be estimated, on the core characteristics of the MA and LLFP loading are different depending on the irradiation Table 1 Monju core specifications Reactor type Sodium-Cooled Loop-Type Thermal power 714MW Electrical power 280MW Operational cycle length 148 days/cycle Core dimensions Equivalent diameter 179cm Height 93cm Burn-up reactivity swing 2.5 % k/kk' Core fuel burn-up (GWd/t) Average 80 Assembly maximum 94 Maximum linear heat rate 360 W/cm Fuel No. of driver assemblies 198 Fuel type UO 2 -PuO 2 Plutonium enrichment (Inner core/ Outer core) Initial core 15/20 Pu fissile % Equilibrium core 16/21 Pu fissile % Fuel inventory Core (U+Pu metal) 5.9ton Blanket (U metal) 17.5ton Cladding outer diameter 0.65cm Cladding thickness 0.047cm Cladding material SUS316 No. of pins per assembly 169 Duct flat-to-flat 11.1cm Duct pitch 11.6cm Blanket Material UO 2 Axial blanket Top length 30cm Bottom length 35cm Radial blanket No. of assemblies 172 Pellet diameter 1.04cm Pin outer diameter 1.16cm No. of pins per assembly 61
4 experiment concepts. Core characteristics were evaluated by two-dimensional R-Z 7 energy groups diffusion calculations taking burn-up effect into account. Seven energy group cross sections were derived from the 70 energy group cross section set JFS-3-J3.2 7) generated from the JENDL-3.2 library 8) by collapsing. The energy group structure adopted is shown in Table 2. The cross sections of the rare earth metals, which were considered to be inevitably mixed up with MAs up to 20%, were synthesized from the individual cross sections as a lumped FP to preserve the total neutron absorption cross section. 1. MA Transmutation Experiment MAs can be incinerated more efficiently in fast spectrum than thermal spectrum because MA nuclides have some threshold reaction and much larger fission-to-capture cross-section ratio in the fast neutron spectrum. Following two concepts of irradiation experiment were assumed for the MA transmutation in this study. The one is MOX fuel mixed with MAs, which is called Homogeneous loading type, assuming the future homogeneous whole core loading of MAs. Rare earth metals were assumed to be included in MAs up to 20%, which were considered to be difficult to separate from MAs completely in the reprocessing procedure. The ratio of MA in the MOX fuel was assumed to be 5 or 10 wt% because MA mixture could cause a deterioration of material properties such as thermal conductivity or melting point. The maximum ratio of MA mixture in the core fuel is also limited to avoid any significant disturbance on the core characteristics. Table 2 7 energy groups structure Energy Group Energy Range MeV-1.35MeV MeV-388keV 3 388keV-86.5keV keV-9.12keV keV-961eV 6 961eV-101eV 7 101eV eV MA Nuclide Table 3 Composition (%) Np 42.7 Am 33.5 Cm 3.8 Rare earth* 20 Composition of MAs Isotopes Composition (%) 237 Np Am Am Am Cm Cm Cm Cm Cm 0.5 *Decontamination factor: La/52, Ce/72, Pr/28, Nd/46, Pm/20, Sm/20, Eu/10, Gd/10 Table 4 Effect of MA transmutation test rig loading on the core characteristics Item 5%MA in MOX fuel 10%MA in MOX fuel 30%MA mixed with MgO Number of test assemblies loaded MA transmutation rate (%/740EFPD) Total amount of transmuted MA (kg/740efpd) Reactivity change (% k/kk ) Burn-up reactivity swing* Coolant density coefficient* Doppler coefficient* Power peaking factor* * Normalized to the Monju reference core (1.0)
5 MA content (kg/assembly) MA content (kg/assembly) MA content (kg/assembly) Homogeneous loading type (5%MA) Homogeneous loading type (10%MA) in the material property aspects such as thermal conductivity or melting point, compared with the homogeneous loading type, while some disadvantage in the nuclear characteristics aspects, such as coolant density coefficient or Doppler reactivity feedback, should be mitigated. The MA assemblies of heterogeneous loading type were assumed to be loaded in the radial blanket region to avoid any significant disturbance on the core characteristics. The core layouts of each case are shown in Fig. 1. MA isotopic composition was estimated based on the LWR spent fuel composition of 33GWd/t burn-up, reprocessed after 5 years cooling-off interval from the discharge. In both cases, nine isotopes of MAs, shown in Table 3, were selected as the targeted nuclides to be transmuted. The irradiation interval was assumed to be 148 EFPDs by 5 cycles as same as the current driver fuels. The results of the core characteristics analysis are shown in Table 4. In case of homogeneous loading type, the 10% MA loading affected the core characteristics more than the 5% of MA loading by double. The resulting MA transmutation rate was evaluated to be 28% (5% MA loading case) to 32% (10% MA loading case). The Doppler coefficient was evaluated to be decreased by 7% and the coolant density coefficient be increased by 10% at the maximum. MAs are strong absorbers and fissile materials especially in the fast neutron spectrum, resulted in harder neutron spectrum. The control rod worth was estimated to be reduced by 1% due to the same reason. Special emphasize was put forward on the power peaking increase by 2% (5% MA loading case) to 4% (10% MA loading case). On the other hand, as for the heterogeneous loading type, the MA transmutation rate was evaluated to be 13%, while the influence of the MA irradiation assembly loading resulted in negligible core characteristics change, compared with the homogeneous loading type. So, it seems to be possible to load more than 18 assemblies without any significant disturbance on the core characteristics. Although the MA transmutation rate is not so large in this case, the heterogeneous loading type in the radial blanket region is preferable for large amount of MA loading. The details of MA content change by irradiation for each isotope are shown in Fig. 3. Fig. 3 Heterogeneous loading type (30%MA) MA content change by irradiation The other is MA diluted with MgO by 30%, which is called Heterogeneous loading type, assuming the future heterogeneous core loading of special MA incineration assemblies. Higher MA mixture ratio can be achieved in this case because this type of MA loading has an advantage 2. LLFP Transmutation Experiment As for the LLFP transmutation experiment, 99 Tc was selected as the typical targeted nuclide, which needs no isotopic separation because of its single isotopic composition. 99 Tc has relatively larger absorption cross section of approximately 1 barn under fast neutron spectrum and has stable chemical form in the reactor core as a metal, which is favorable for in-core irradiation. Experimental assemblies with both 99 Tc pins and moderator (ZrH 1.7 ) pins were assumed to be irradiated in the radial blanket region. The number of test rigs loaded was assumed to be 54 at the maximum. The ratio of the moderator pins was varied parametrically from 0% (without
6 100% Tc-99 pins 78.7% Tc-99 pins 60.7% Tc-99 pins ZrH 1.7 pin 99 Tc pin Fig. 4 Pin arrangement in the test rigs for 99 Tc irradiation experiments Absorption cross section (barn) Tc absorption cross section 2.0 Total flux Volume ratio of 99 Tc ; [ 99 Tc / ( 99 Tc + ZrH )] Total flux ( n/cm 2 /sec) Power density (W/cc) Reference 99 Tc 100% 99 Tc 60.7% Power peak Distance from center (cm) Fig. 5 Correlation of total flux and absorption cross section on the ratio of 99 Tc Fig. 6 Power distribution in the core for 99 Tc transmutation experiment Table 5 Effect of LLFP(Tc-99) transmutation test rig loading on the core characteristics Item 100% 99 Tc pins 78.7% 99 Tc pins 60.7% 99 Tc pins Number of test assemblies loaded LLFP transmutation rate (%/year) Amount of transmuted LLFP (kg/ year) Reactivity change (% k/kk ) Burn-up reactivity swing* Sodium void reactivity* * Normalized to the Monju reference core (1.0) moderator) to 40%, as shown in Fig. 4, to investigate the effect of the moderator on the transmutation rate and the possible amount of loaded 99 Tc. Core layout is shown in Fig. 1. The results of the core characteristics analysis are shown in Table 5. The transmutation rate was evaluated to be 0.7%/year for without-moderator case and 1.2%/year to 1.4%/year for with-moderator case. The reactivity was decreased by 3.3% k/kk in case of 99 Tc loading without moderator, while the reactivity decrease with moderator was
7 estimated to be 4.5% k/kk. Sodium void reactivity was reduced approximately by half compared with the reference core in case with moderator. The disturbance on the core characteristics seemed to be not negligible in this maximum loading case. The total amount of transmuted 99 Tc per year remained as the same level in both the with-moderator and the without-moderator cases, in spite the transmutation rate was improved in the with-moderator case. This comes from the fact that the increase of the moderator pins limits the number of 99 Tc pins resulting in decrease of the total amount of loaded 99 Tc. Figure 5 shows the correlation between the moderator ratio and the effective absorption cross section. The higher moderator ratio leads to softer neutron energy spectrum, and results in larger effective absorption cross section. On the other hand, in the with-moderator case, a steep power skew at the adjacent fuel assemblies was observed around the test rigs. Some design modification, such as local adjustment of plutonium enrichment, etc. might be necessary to mitigate this power skew, shown in Fig. 6. As a result, the number of test assemblies was found to be limited below one third or one sixth of the maximum loading case, for example, to avoid any significant disturbance on the core characteristics. IV. Conclusion 1. MA Transmutation Experiment In case of MA incineration experiment in the Monju core, nine test assemblies with MOX fuel mixed with 5% MA loaded in the core region seems to be feasible, taking into account the power peaking increase. In case of radial blanket region loading, over eighteen test assemblies with MA diluted with MgO by 30% seems to be feasible without any significant disturbance on the core characteristics. Certain transmutation rate of over 10% to 30% can be achieved in both cases. So the options can be chosen based on the purpose of the experiment. 2. LLFP Transmutation Experiment In case of LLFP ( 99 Tc) transmutation experiment in the Monju core, the number of test assemblies, fifty four at the maximum, loaded in the radial blanket region seems to be limited below one third or one sixth of the maximum loading case, for example, to avoid significant disturbance on the core characteristics. Some design modifications might be necessary to mitigate the steep power skew around the test rigs, especially in the with-moderator case. The irradiation experiment seems to be feasible under these conditions. Transmutation rate of approximately 0.7%/year to 1.4%/year can be obtained. This implies the possibility of profitable experiment in the Monju core for LLFP transmutation. The capability of the Monju core for MA/LLFP transmutation irradiation experiment has been confirmed, which contributes to the future commercialization of FBR technology. So, Monju should be restarted at the earliest stage possible not only for this purpose but also to establish the sodium handling technology and to demonstrate its reliability as a power station. References 1) T. Wakabayashi, et al., Nucl. Technol., 118, 14 (1997). 2) M. Yamaoka, M. Ishikawa, T. Wakabayashi, et al., Proc. Int. Fast Reactors and Related Fuel Cycles, FR 91, Kyoto, Vo. IV (1991). 3) M. Yamaoka, T. Wakabayashi, Proc. Int. Conf. Design and Safety of Advanced Nuclear Power Plants, ANP 92, Tokyo, Japan, I3.3-1 (1992). 4) K. Fujimura, et al., J. Nucl. Sci. Technol., 38[10], 879 (2001). 5) A. Mizutani., Trans. Am. Nucl. Soc., 81, 294 (1999). 6) M. Salvatores, I. Slessarev, A. Tchistiakov, et al., Nucl. Sci. Eng., 130, 309 (1998). 7) H. Takano, Proc Symp. on Nucl. Data, Tokai, Japan, JAERI-Conf , 47 (1995). 8) T. Nakagawa, et al., J. Nucl. Sci. Technol., 32, 1259 (1995).
Available online at ScienceDirect. Energy Procedia 71 (2015 )
Available online at www.sciencedirect.com ScienceDirect Energy Procedia 71 (2015 ) 97 105 The Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4 High-Safety Fast Reactor Core Concepts
More informationTRANSMUTATION OF CESIUM-135 WITH FAST REACTORS
TRANSMUTATION OF CESIUM-3 WITH FAST REACTORS Shigeo Ohki and Naoyuki Takaki O-arai Engineering Center Japan Nuclear Cycle Development Institute (JNC) 42, Narita-cho, O-arai-machi, Higashi-Ibaraki-gun,
More informationO-arai Engineering Center Power Reactor and Nuclear Fuel Development Corporation 4002 Narita, O-arai-machi, Ibaraki-ken JAPAN ABSTRACT
Characteristics of TRU Transmutation in an LMFBR M. Yamaoka, M. Ishikawa, and T. Wakabayashi O-arai Engineering Center Power Reactor and Nuclear Fuel Development Corporation 4002 Narita, O-arai-machi,
More informationJOYO MK-III Performance Test at Low Power and Its Analysis
PHYSOR 200 -The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, Illinois, April 25-29, 200, on CD-ROM, American Nuclear Society, Lagrange Park, IL. (200) JOYO MK-III Performance
More informationSTATUS OF TRANSMUTATION STUDIES IN A FAST REACTOR AT JNC
STATUS OF TRANSMUTATION STUDIES IN A FAST REACTOR AT JNC Toshio Wakabayashi Japan Nuclear Cycle Development Institute (JNC) 9-13, 1-chome, Akasaka, Minato-ku, Tokyo, Japan Abstract This paper presents
More informationTarget accuracy of MA nuclear data and progress in validation by post irradiation experiments with the fast reactor JOYO
Target accuracy of MA nuclear data and progress in validation by post irradiation experiments with the fast reactor JOYO Shigeo OHKI, Kenji YOKOYAMA, Kazuyuki NUMATA *, and Tomoyuki JIN * Oarai Engineering
More information3.12 Development of Burn-up Calculation System for Fusion-Fission Hybrid Reactor
3.12 Development of Burn-up Calculation System for Fusion-Fission Hybrid Reactor M. Matsunaka, S. Shido, K. Kondo, H. Miyamaru, I. Murata Division of Electrical, Electronic and Information Engineering,
More informationSensitivity and Uncertainty Analysis Methodologies for Fast Reactor Physics and Design at JAEA
Sensitivity and Uncertainty Analysis Methodologies for Fast Reactor Physics and Design at JAEA Kick off meeting of NEA Expert Group on Uncertainty Analysis for Criticality Safety Assessment IRSN, France
More informationRecycling Spent Nuclear Fuel Option for Nuclear Sustainability and more proliferation resistance In FBR
Recycling Spent Nuclear Fuel Option for Nuclear Sustainability and more proliferation resistance In FBR SIDIK PERMANA a, DWI IRWANTO a, MITSUTOSHI SUZUKI b, MASAKI SAITO c, ZAKI SUUD a a Nuclear Physics
More informationError Estimation for ADS Nuclear Properties by using Nuclear Data Covariances
Error Estimation for ADS Nuclear Properties by using Nuclear Data Covariances Kasufumi TSUJIMOTO Center for Proton Accelerator Facilities, Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken
More informationStudy of Burnup Reactivity and Isotopic Inventories in REBUS Program
Study of Burnup Reactivity and Isotopic Inventories in REBUS Program T. Yamamoto 1, Y. Ando 1, K. Sakurada 2, Y. Hayashi 2, and K. Azekura 3 1 Japan Nuclear Energy Safety Organization (JNES) 2 Toshiba
More informationCiclo combustibile, scorie, accelerator driven system
Ciclo combustibile, scorie, accelerator driven system M. Carta, C. Artioli ENEA Fusione e Fissione Nucleare: stato e prospettive sulle fonti energetiche nucleari per il futuro Layout of the presentation!
More informationAdvanced Heavy Water Reactor. Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA
Advanced Heavy Water Reactor Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA Design objectives of AHWR The Advanced Heavy Water Reactor (AHWR) is a unique reactor designed
More informationREACTOR PHYSICS ASPECTS OF PLUTONIUM RECYCLING IN PWRs
REACTOR PHYSICS ASPECTS OF PLUTONIUM RECYCLING IN s Present address: J.L. Kloosterman Interfaculty Reactor Institute Delft University of Technology Mekelweg 15, NL-2629 JB Delft, the Netherlands Fax: ++31
More informationStatus of J-PARC Transmutation Experimental Facility
Status of J-PARC Transmutation Experimental Facility 10 th OECD/NEA Information Exchange Meeting for Actinide and Fission Product Partitioning and Transmutation 2008.10.9 Japan Atomic Energy Agency Toshinobu
More informationTHORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR
International Conference Nuclear Energy for New Europe 2005 Bled, Slovenia, September 5-8, 2005 ABSTRACT THORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR Boris Bergelson, Alexander Gerasimov Institute
More informationFeasibility of MA Transmutation by (MA, Zr)H x in Radial Blanket Region of Fast Reactor and Plan of Technology Development
1 564 Feasibility of MA Transmutation by (MA, Zr)H x in Radial Blanket Region of Fast Reactor and Plan of Technology Development Kazumi IKEDA¹, Kenji KONASHI 2, Kazuo IKEDA 3, Kunihiro ITOH 3, Fumiki MIZUSAKO
More informationLesson 14: Reactivity Variations and Control
Lesson 14: Reactivity Variations and Control Reactivity Variations External, Internal Short-term Variations Reactivity Feedbacks Reactivity Coefficients and Safety Medium-term Variations Xe 135 Poisoning
More informationReduction of Radioactive Waste by Accelerators
October 9-10, 2014 International Symposium on Present Status and Future Perspective for Reducing Radioactive Waste - Aiming for Zero-Release - Reduction of Radioactive Waste by Accelerators Hiroyuki Oigawa
More informationNumerical analysis on element creation by nuclear transmutation of fission products
NUCLEAR SCIENCE AND TECHNIQUES 26, S10311 (2015) Numerical analysis on element creation by nuclear transmutation of fission products Atsunori Terashima 1, and Masaki Ozawa 2 1 Department of Nuclear Engineering,
More informationNuclear Data for Emergency Preparedness of Nuclear Power Plants Evaluation of Radioactivity Inventory in PWR using JENDL 3.3
Nuclear Data for Emergency Preparedness of Nuclear Power Plants Evaluation of Radioactivity Inventory in PWR using JENDL 3.3 Yoshitaka Yoshida, Itsuro Kimura Institute of Nuclear Technology, Institute
More informationWorking Party on Pu-MOX fuel physics and innovative fuel cycles (WPPR)
R&D Needs in Nuclear Science 6-8th November, 2002 OECD/NEA, Paris Working Party on Pu-MOX fuel physics and innovative fuel cycles (WPPR) Hideki Takano Japan Atomic Energy Research Institute, Japan Introduction(1)
More informationNeutronic analysis of SFR lattices: Serpent vs. HELIOS-2
Neutronic analysis of SFR lattices: Serpent vs. HELIOS-2 E. Fridman 1, R. Rachamin 1, C. Wemple 2 1 Helmholtz Zentrum Dresden Rossendorf 2 Studsvik Scandpower Inc. Text optional: Institutsname Prof. Dr.
More informationActivation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB
Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB K. M. Feng (Southwestern Institute of Physics, China) Presented at 8th IAEA Technical Meeting on Fusion Power Plant Safety
More informationTHE INTEGRATION OF FAST REACTOR TO THE FUEL CYCLE IN SLOVAKIA
THE INTEGRATION OF FAST REACTOR TO THE FUEL CYCLE IN SLOVAKIA Radoslav ZAJAC, Petr DARILEK VUJE, Inc. Okruzna 5, SK-91864 Trnava, Slovakia Tel: +421 33 599 1316, Fax: +421 33 599 1191, Email: zajacr@vuje.sk,
More informationA-BAQUS A multi-entry graph assisting the neutronic design of an ADS Case study: EFIT
Fifth International Workshop on the Utilisation and Reliability of High Power Proton Accelerator SCK-CEN Mol, Belgium 6-9 May 7 A-BAQUS A multi-entry graph assisting the neutronic design of an ADS Case
More informationNeutronic Comparison Study Between Pb(208)-Bi and Pb(208) as a Coolant In The Fast Reactor With Modified CANDLE Burn up Scheme.
Journal of Physics: Conference Series PAPER OPEN ACCESS Neutronic Comparison Study Between Pb(208)-Bi and Pb(208) as a Coolant In The Fast Reactor With Modified CANDLE Burn up Scheme. To cite this article:
More informationStudy on SiC Components to Improve the Neutron Economy in HTGR
Study on SiC Components to Improve the Neutron Economy in HTGR Piyatida TRINURUK and Assoc.Prof.Dr. Toru OBARA Department of Nuclear Engineering Research Laboratory for Nuclear Reactors Tokyo Institute
More informationRequests on Nuclear Data in the Backend Field through PIE Analysis
Requests on Nuclear Data in the Backend Field through PIE Analysis Yoshihira Ando 1), Yasushi Ohkawachi 2) 1) TOSHIBA Corporation Power System & Services Company Power & Industrial Systems Research & Development
More informationAnalysis of the Neutronic Characteristics of GFR-2400 Fast Reactor Using MCNPX Transport Code
Amr Ibrahim, et al. Arab J. Nucl. Sci. Appl, Vol 51, 1, 177-188 The Egyptian Arab Journal of Nuclear Sciences and Applications (2018) Society of Nuclear Vol 51, 1, (177-188) 2018 Sciences and Applications
More informationTitle. Author(s)Chiba, Go; Tsuji, Masashi; Narabayashi, Tadashi. CitationAnnals of nuclear energy, 65: Issue Date Doc URL.
Title Photon transport effect on intra-subassembly thermal Author(s)Chiba, Go; Tsuji, Masashi; Narabayashi, Tadashi CitationAnnals of nuclear energy, 65: 41-46 Issue Date 2014-03 Doc URL http://hdl.handle.net/2115/55139
More informationStudy on Nuclear Transmutation of Nuclear Waste by 14 MeV Neutrons )
Study on Nuclear Transmutation of Nuclear Waste by 14 MeV Neutrons ) Takanori KITADA, Atsuki UMEMURA and Kohei TAKAHASHI Osaka University, Graduate School of Engineering, Division of Sustainable Energy
More informationFuel cycle studies on minor actinide transmutation in Generation IV fast reactors
Fuel cycle studies on minor actinide transmutation in Generation IV fast reactors M. Halász, M. Szieberth, S. Fehér Budapest University of Technology and Economics, Institute of Nuclear Techniques Contents
More informationTRANSMUTATION OF AMERICIUM AND CURIUM: REVIEW OF SOLUTIONS AND IMPACTS. Abstract
TRANSMUTATION OF AMERICIUM AND CURIUM: REVIEW OF SOLUTIONS AND IMPACTS M. Delpech, J. Tommasi, A. Zaetta DER/SPRC, CEA M. Salvatores DRN/PP, CEA H. Mouney EDF/DE G. Vambenepe EDF/SEPTEN Abstract Several
More informationSUB-CHAPTER D.1. SUMMARY DESCRIPTION
PAGE : 1 / 12 CHAPTER D. REACTOR AND CORE SUB-CHAPTER D.1. SUMMARY DESCRIPTION Chapter D describes the nuclear, hydraulic and thermal characteristics of the reactor, the proposals made at the present stage
More informationIncineration of Plutonium in PWR Using Hydride Fuel
Incineration of Plutonium in PWR Using Hydride Fuel Francesco Ganda and Ehud Greenspan University of California, Berkeley ARWIF-2005 Oak-Ridge, TN February 16-18, 2005 Pu transmutation overview Many approaches
More informationTRANSMUTATION PERFORMANCE OF MOLTEN SALT VERSUS SOLID FUEL REACTORS (DRAFT)
15 th International Conference on Nuclear Engineering Nagoya, Japan, April 22-26, 2007 ICONE15-10515 TRANSMUTATION PERFORMANCE OF MOLTEN SALT VERSUS SOLID FUEL REACTORS (DRAFT) Björn Becker University
More informationASSESSMENT OF THE EQUILIBRIUM STATE IN REACTOR-BASED PLUTONIUM OR TRANSURANICS MULTI-RECYCLING
ASSESSMENT OF THE EQUILIBRIUM STATE IN REACTOR-BASED PLUTONIUM OR TRANSURANICS MULTI-RECYCLING T.K. Kim, T.A. Taiwo, J.A. Stillman, R.N. Hill and P.J. Finck Argonne National Laboratory, U.S. Abstract An
More informationCambridge University Press An Introduction to the Engineering of Fast Nuclear Reactors Anthony M. Judd Excerpt More information
INTRODUCTION WHAT FAST REACTORS CAN DO Chain Reactions Early in 1939 Meitner and Frisch suggested that the correct interpretation of the results observed when uranium is bombarded with neutrons is that
More informationNuclear transmutation strategies for management of long-lived fission products
PRAMANA c Indian Academy of Sciences Vol. 85, No. 3 journal of September 2015 physics pp. 517 523 Nuclear transmutation strategies for management of long-lived fission products S KAILAS 1,2,, M HEMALATHA
More informationCALCULATIONS OF DIFFERENT TRANSMUTATION CONCEPTS
NEA NUCLEAR SCIENCE COMMITTEE CALCULATIONS OF DIFFERENT TRANSMUTATION CONCEPTS An International Benchmark Exercise February 2000 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC AND CO-OPERATION DEVELOPMENT
More informationEnglish text only NUCLEAR ENERGY AGENCY NUCLEAR SCIENCE COMMITTEE
Unclassified NEA/NSC/DOC(2007)9 NEA/NSC/DOC(2007)9 Unclassified Organisation de Coopération et de Développement Economiques Organisation for Economic Co-operation and Development 14-Dec-2007 English text
More informationAdaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source
Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source E. Hoffman, W. Stacey, G. Kessler, D. Ulevich, J. Mandrekas, A. Mauer, C. Kirby, D. Stopp, J. Noble
More informationBN-800 HISTORY AND PERSPECTIVE
BN-800 HISTORY AND PERSPECTIVE I. Yu. Krivitski Institute for Physics and Power Engineering, Russia, e-mail:stogov@ippe.obninsk.ru ABSTRACT The sodium cooled fast reactors are one of the most developed
More informationAnalytical Validation of Uncertainty in Reactor Physics Parameters for Nuclear Transmutation Systems
Journal of Nuclear Science and Technology ISSN: 22-3131 (Print) 1881-1248 (Online) Journal homepage: http://www.tandfonline.com/loi/tnst2 Analytical Validation of Uncertainty in Reactor Physics Parameters
More informationFusion/transmutation reactor studies based on the spherical torus concept
FT/P1-7, FEC 2004 Fusion/transmutation reactor studies based on the spherical torus concept K.M. Feng, J.H. Huang, B.Q. Deng, G.S. Zhang, G. Hu, Z.X. Li, X.Y. Wang, T. Yuan, Z. Chen Southwestern Institute
More informationEvaluation of Neutron Physics Parameters and Reactivity Coefficients for Sodium Cooled Fast Reactors
Evaluation of Neutron Physics Parameters and Reactivity Coefficients for Sodium Cooled Fast Reactors A. Ponomarev, C.H.M. Broeders, R. Dagan, M. Becker Institute for Neutron Physics and Reactor Technology,
More informationSimulating the Behaviour of the Fast Reactor JOYO
IYNC 2008 Interlaken, Switzerland, 20 26 September 2008 Paper No. 163 Simulating the Behaviour of the Fast Reactor JOYO ABSTRACT Pauli Juutilainen VTT Technical Research Centre of Finland, P.O. Box 1000,
More informationQuestion to the class: What are the pros, cons, and uncertainties of using nuclear power?
Energy and Society Week 11 Section Handout Section Outline: 1. Rough sketch of nuclear power (15 minutes) 2. Radioactive decay (10 minutes) 3. Nuclear practice problems or a discussion of the appropriate
More information(CE~RN, G!E21ZZMA?ZOEWSPRC)
DRN PROGRAM ON LONG-LIVED WASTE TRANSMUTATION STUDIES : TRANSMUTATION POTENTIAL OF CURRENT AND INNOVATIVE SYSTEMS M. Salvatores, A. Zaetta, C. Girard, M. Delpech, I. Slessarev, J. Tommasi (CE~RN, G!E21ZZMA?ZOEWSPRC)
More informationFundamentals of Nuclear Power. Original slides provided by Dr. Daniel Holland
Fundamentals of Nuclear Power Original slides provided by Dr. Daniel Holland Nuclear Fission We convert mass into energy by breaking large atoms (usually Uranium) into smaller atoms. Note the increases
More informationProduction. David Nusbaum Project on Managing the Atom, Belfer Center October 4, 2011
Production David Nusbaum Project on Managing the Atom, Belfer Center October 4, 2011 Where are we? Nuclear Fuel Cycle Background Pu- Radioactive, chemical element, of the actinoid series of the periodic
More informationPower Installations based on Activated Nuclear Reactions of Fission and Synthesis
Yu.V. Grigoriev 1,2, A.V. Novikov-Borodin 1 1 Institute for Nuclear Research RAS, Moscow, Russia 2 Joint Institute for Nuclear Research, Dubna, Russia Power Installations based on Activated Nuclear Reactions
More informationTransmutation of Minor Actinides in a Spherical
1 Transmutation of Minor Actinides in a Spherical Torus Tokamak Fusion Reactor Feng Kaiming Zhang Guoshu Fusion energy will be a long-term energy source. Great efforts have been devoted to fusion research
More informationNuclear Data for Reactor Physics: Cross Sections and Level Densities in in the Actinide Region. J.N. Wilson Institut de Physique Nucléaire, Orsay
Nuclear Data for Reactor Physics: Cross Sections and Level Densities in in the Actinide Region J.N. Wilson Institut de Physique Nucléaire, Orsay Talk Plan Talk Plan The importance of innovative nuclear
More informationPrototypes and fuel cycle options including transmutation
A S T R I D Prototypes and fuel cycle options including transmutation General introduction, GEN IV fast reactors Transmutation demonstration Fuel cycle Conclusions www.cea.fr DEN/CAD/DER/CPA Jean-Paul
More informationDEVELOPMENT OF HIGH RESOLUTION X-RAY CT TECHNIQUE FOR IRRADIATED FUEL ASSEMBLY
More Info at Open Access Database www.ndt.net/?id=18598 DEVELOPMENT OF HIGH RESOLUTION X-RAY CT TECHNIQUE FOR IRRADIATED FUEL ASSEMBLY A. Ishimi, K. Katsuyama, H. Kodaka, H. Furuya Japan Atomic Energy
More informationProliferation-Proof Uranium/Plutonium Fuel Cycles Safeguards and Non-Proliferation
Proliferation-Proof Uranium/Plutonium Fuel Cycles Safeguards and Non-Proliferation SUB Hamburg by Gunther KeBler A 2012/7138 Scientific Publishing id- Contents 1 Nuclear Proliferation and IAEA-Safeguards
More informationDevelopment of depletion models for radionuclide inventory, decay heat and source term estimation in discharged fuel
Development of depletion models for radionuclide inventory, decay heat and source term estimation in discharged fuel S. Caruso, A. Shama, M. M. Gutierrez National Cooperative for the Disposal of Radioactive
More informationNuclear Fission. 1/v Fast neutrons. U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b.
Nuclear Fission 1/v Fast neutrons should be moderated. 235 U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b. Fission Barriers 1 Nuclear Fission Q for 235 U + n 236 U
More informationExternal neutrons sources for fissionbased
External neutrons sources for fissionbased reactors S. David, CNRS/IN2P3/IPN Orsay sdavid@ipno.in2p3.fr S. David,external neutron source for fission-based reactors, IZEST, Orsay, Nov 2017 1 World Energy
More informationProgress in Conceptual Research on Fusion Fission Hybrid Reactor for Energy (FFHR-E)
Progress in Conceptual Research on Fusion Fission Hybrid Reactor for Energy (FFHR-E) Xue-Ming Shi Xian-Jue Peng Institute of Applied Physics and Computational Mathematics(IAPCM), BeiJing, China December
More informationREACTOR PHYSICS CALCULATIONS ON MOX FUEL IN BOILING WATER REACTORS (BWRs)
REACTOR PHYSICS CALCULATIONS ON MOX FUEL IN BOILING ATER REACTORS (BRs) Christophe Demazière Chalmers University of Technology Department of Reactor Physics SE-42 96 Gothenburg Sweden Abstract The loading
More informationVERIFICATION OFENDF/B-VII.0, ENDF/B-VII.1 AND JENDL-4.0 NUCLEAR DATA LIBRARIES FOR CRITICALITY CALCULATIONS USING NEA/NSC BENCHMARKS
VERIFICATION OFENDF/B-VII.0, ENDF/B-VII.1 AND JENDL-4.0 NUCLEAR DATA LIBRARIES FOR CRITICALITY CALCULATIONS USING NEA/NSC BENCHMARKS Amine Bouhaddane 1, Gabriel Farkas 1, Ján Haščík 1, Vladimír Slugeň
More information2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea
Neutronic evaluation of thorium-uranium fuel in heavy water research reactor HADI SHAMORADIFAR 1,*, BEHZAD TEIMURI 2, PARVIZ PARVARESH 1, SAEED MOHAMMADI 1 1 Department of Nuclear physics, Payame Noor
More informationThe Current Status of R&D for Accelerator-driven System at JAERI
GENES4/ANP2003, Sep. 15-19, 2003, Kyoto, JAPAN Paper 1184 The Current Status of R&D for Accelerator-driven System at JAERI Toshinobu Sasa *, Hiroyuki Oigawa, Kazufumi Tsujimoto, Kenji Nishihara, Makoto
More informationReactivity Coefficients
Reactivity Coefficients B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec. 2015 September 1 Reactivity Changes In studying kinetics, we have seen
More informationSensitivity Analysis of Gas-cooled Fast Reactor
Sensitivity Analysis of Gas-cooled Fast Reactor Jakub Lüley, Štefan Čerba, Branislav Vrban, Ján Haščík Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava Ilkovičova
More informationIMPACT OF THE FISSION YIELD COVARIANCE DATA IN BURN-UP CALCULATIONS
IMPACT OF THE FISSION YIELD COVARIANCE DATA IN BRN-P CALCLATIONS O. Cabellos, D. Piedra, Carlos J. Diez Department of Nuclear Engineering, niversidad Politécnica de Madrid, Spain E-mail: oscar.cabellos@upm.es
More informationKr-85m activity as burnup measurement indicator in a pebble bed reactor based on ORIGEN2.1 Computer Simulation
Journal of Physics: Conference Series PAPER OPEN ACCESS Kr-85m activity as burnup measurement indicator in a pebble bed reactor based on ORIGEN2.1 Computer Simulation To cite this article: I Husnayani
More informationINTRODUCTION TO NUCLEAR REACTORS AND NUCLEAR POWER GENERATION. Atsushi TAKEDA & Hisao EDA
INTRODUCTION TO NUCLEAR REACTORS AND NUCLEAR POWER GENERATION Atsushi TAKEDA & Hisao EDA 1 CONTENTS The first step toward nuclear power Physics of nuclear fission Sustained chain reaction in nuclear reactor
More informationMULTI-RECYCLING OF TRANSURANIC ELEMENTS IN A MODIFIED PWR FUEL ASSEMBLY. A Thesis ALEX CARL CHAMBERS
MULTI-RECYCLING OF TRANSURANIC ELEMENTS IN A MODIFIED PWR FUEL ASSEMBLY A Thesis by ALEX CARL CHAMBERS Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the
More informationResearch and Development to Reduce Radioactive Waste by Accelerator
Research and Development to Reduce Radioactive Waste by Accelerator Current Status and Prospects for Partitioning and Transmutation Technology Japan Atomic Energy Agency Introduction We humans need to
More informationTRANSMUTATION OF LONG-LIVED NUCLIDES IN THE FUEL CYCLE OF BREST-TYPE REACTORS. A.V. Lopatkin, V.V. Orlov, A.I. Filin (RDIPE, Moscow, Russia)
TRANSMUTATION OF LONG-LIVE NUCLIES IN THE FUEL CYCLE OF BREST-TYPE REACTORS A.V. Lopatkin, V.V. Orlov, A.I. Filin RIPE, Moscow, Russia) 947 1. Background Radiation background is an integral part of nature
More informationParametric Studies of the Effect of MOx Environment and Control Rods for PWR-UOx Burnup Credit Implementation
42 Parametric Studies of the Effect of MOx Environment and Control Rods for PWR-UOx Burnup Credit Implementation Anne BARREAU 1*, Bénédicte ROQUE 1, Pierre MARIMBEAU 1, Christophe VENARD 1 Philippe BIOUX
More informationUsers manual of CBZ/FRBurnerRZ: A module for fast reactor core design
Users manual of CBZ/FRBurnerRZ: A module for fast reactor core design Go CHIBA May 25, 2018 Contents 1 Brief summary of FRBurnerRZ 2 2 Preparation of input deck 2 2.1 Preparation of fuel pellet composition
More informationTesting of Nuclear Data Libraries for Fission Products
Testing of Nuclear Data Libraries for Fission Products A.V. Ignatyuk, S.M. Bednyakov, V.N. Koshcheev, V.N. Manokhin, G.N. Manturov, and G.Ya. Tertuchny Institute of Physics and Power Engineering, 242 Obninsk,
More informationmore ?Learning about plutonium
?Learning about plutonium more What is plutonium? Plutonium (PU) is a hard white metal that looks like iron. It melts at 640 Celsius, turns into plutonium oxide when exposed to air and can catch fire.
More informationCritical Experiment Analyses by CHAPLET-3D Code in Two- and Three-Dimensional Core Models
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 42, No. 1, p. 101 108 (January 2005) TECHNICAL REPORT Critical Experiment Analyses by CHAPLET-3D Code in Two- and Three-Dimensional Core Models Shinya KOSAKA
More informationChapter 6 Development of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9 9 Fuel
Chapter 6 Development of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9 9 Fuel Kenya Suyama, Gunzo Uchiyama, Hiroyuki Fukaya, Miki Umeda, Toru Yamamoto, and
More informationNeutronic Issues and Ways to Resolve Them. P.A. Fomichenko National Research Center Kurchatov Institute Yu.P. Sukharev JSC Afrikantov OKBM,
GT-MHR Project High-Temperature Reactor Neutronic Issues and Ways to Resolve Them P.A. Fomichenko National Research Center Kurchatov Institute Yu.P. Sukharev JSC Afrikantov OKBM, GT-MHR PROJECT MISSION
More informationSafety analyses of criticality control systems for transportation packages include an assumption
Isotopic Validation for PWR Actinide-OD-!y Burnup Credit Using Yankee Rowe Data INTRODUCTION Safety analyses of criticality control systems for transportation packages include an assumption that the spent
More informationSIMPLIFIED BENCHMARK SPECIFICATION BASED ON #2670 ISTC VVER PIE. Ludmila Markova Frantisek Havluj NRI Rez, Czech Republic ABSTRACT
12 th Meeting of AER Working Group E on 'Physical Problems of Spent Fuel, Radwaste and Nuclear Power Plants Decommissioning' Modra, Slovakia, April 16-18, 2007 SIMPLIFIED BENCHMARK SPECIFICATION BASED
More informationNuclear Fuel Cycle and WebKOrigen
10th Nuclear Science Training Course with NUCLEONICA Institute of Nuclear Science of Ege University, Cesme, Izmir, Turkey, 8th-10th October 2008 Nuclear Fuel Cycle and WebKOrigen Jean Galy European Commission
More informationCRITICALITY DETECTION METHOD BASED ON FP GAMMA RADIATION MEASUREMENT
CRITICALITY DETECTION METHOD BASED ON FP GAMMA RADIATION MEASREMENT Yoshitaka Naito, Kazuo Azekura NAIS Co., inc. Muramatsu 416, Tokaimura, Ibaraki-ken, Japan 319-1112 ynaito@nais.ne.jp azekura@nais.ne.jp
More informationPWR AND WWER MOX BENCHMARK CALCULATION BY HELIOS
PWR AND WWER MOX BENCHMARK CALCULATION BY HELIOS Radoslav ZAJAC 1,2), Petr DARILEK 1), Vladimir NECAS 2) 1 VUJE, Inc., Okruzna 5, 918 64 Trnava, Slovakia; zajacr@vuje.sk, darilek@vuje.sk 2 Slovak University
More informationThorium as a Nuclear Fuel
Thorium as a Nuclear Fuel Course 22.251 Fall 2005 Massachusetts Institute of Technology Department of Nuclear Engineering 22.351 Thorium 1 Earth Energy Resources Commercial Energy Resources in India Electricity
More informationNEUTRON PHYSICAL ANALYSIS OF SIX ENERGETIC FAST REACTORS
NEUTRON PHYSICAL ANALYSIS OF SIX ENERGETIC FAST REACTORS Peter Vertes Hungarian Academy of Sciences, Centre for Energy Research ABSTRACT Numerous fast reactor constructions have been appeared world-wide
More informationTroitsk ADS project S.Sidorkin, E.Koptelov, L.Kravchuk, A.Rogov
Troitsk ADS project S.Sidorkin, E.Koptelov, L.Kravchuk, A.Rogov Institute for Nuclear Research RAS, Moscow, Russia Outline Linac and experimental complex Pulse neutron sources and its infrastructure Development
More informationUppsala University. Access to the published version may require subscription.
Uppsala University This is an accepted version of a paper published in Annals of Nuclear Energy. This paper has been peer-reviewed but does not include the final publisher proof-corrections or journal
More informationBurn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code
NUKLEONIKA 2014;59(4):129136 doi: 10.2478/nuka-2014-0017 ORIGINAL PAPER Burn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code Zohreh Gholamzadeh,
More informationOptimisation of the Nuclear Reactor Neutron Spectrum for the Transmutation of Am 241 and Np 237
Optimisation of the Nuclear Reactor Neutron Spectrum for the Transmutation of Am 241 and Np 237 Sarah M. Don under the direction of Professor Michael J. Driscoll and Bo Feng Nuclear Science and Engineering
More informationMinor Actinides Transmutation: ADS and Power Fast Reactors
Nuclear 2011 Piteşti May 25-27, 2011 Minor Actinides Transmutation: ADS and Power Fast Reactors Carlo Artioli carlo.artioli@enea.it Outline - Wastes and Minor Actines - EFIT, the ADS of EU EUROTRANS Project
More informationTAGS and FP Decay Heat Calculations( ) -Impact on the LOCA Condition Decay Heat-
TAGS and FP Decay Heat Calculations( ) -Impact on the LOCA Condition Decay Heat- Akira HONMA, Tadashi YOSHIDA Musashi Institute of Technology, Tamazutsumi 1-28-1, Setagaya-ku, Tokyo 158-8557, Japan e-mail:
More informationIAEA-TECDOC Nuclear Fuel Cycle Simulation System (VISTA)
IAEA-TECDOC-1535 Nuclear Fuel Cycle Simulation System (VISTA) February 2007 IAEA-TECDOC-1535 Nuclear Fuel Cycle Simulation System (VISTA) February 2007 The originating Section of this publication in the
More informationCore Physics Second Part How We Calculate LWRs
Core Physics Second Part How We Calculate LWRs Dr. E. E. Pilat MIT NSED CANES Center for Advanced Nuclear Energy Systems Method of Attack Important nuclides Course of calc Point calc(pd + N) ϕ dn/dt N
More informationORIENT-CYCLE EVOLUTIONAL RECYCLE CONCEPT WITH FAST REACTOR FOR MINIMISING HIGH-LEVEL WASTE
ORIENT-CYCLE EVOLUTIONAL RECYCLE CONCEPT WITH FAST REACTOR FOR MINIMISING HIGH-LEVEL WASTE Naoyuki Takaki, Yoshihiko Shinoda, Masayuki Watanabe and Kazuo Yoshida 1 Japan Nuclear Cycle Development Institute
More informationInvestigation of Nuclear Data Accuracy for the Accelerator- Driven System with Minor Actinide Fuel
Investigation of Nuclear Data Accuracy for the Accelerator- Driven System with Minor Actinide Fuel Kenji Nishihara, Takanori Sugawara, Hiroki Iwamoto JAEA, Japan Francisco Alvarez Velarde CIEMAT, Spain
More informationPIA and REWIND: Two New Methodologies for Cross Section Adjustment. G. Palmiotti and M. Salvatores
PIA and REWIND: Two New Methodologies for Cross Section Adjustment G. Palmiotti and M. Salvatores Nuclear Systems Design and Analysis Division, Idaho National Laboratory, P.O. Box 1625, MS 3860, Idaho
More informationImprovements of Isotopic Ratios Prediction through Takahama-3 Chemical Assays with the JEFF3.0 Nuclear Data Library
PHYSOR 2004 -The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, Illinois, April 25-29, 2004, on CD-ROM, American Nuclear Society, Lagrange Park, IL. (2004) Improvements
More information