Annals Of Nuclear Energy Research Articles

06/00099 Sensitivity analysis of multiplication rate for subcritical systems: Kobayashi, K. Annals of Nuclear Energy, 2005, 32, (8), 777–794

06/00099 Sensitivity analysis of multiplication rate for subcritical systems: Kobayashi, K. Annals of Nuclear Energy, 2005, 32, (8), 777–794

06/00408 A novel channel selection method for CANDUrefuelling based on the BPANN and GA techniques: Huo, X. and Xie, Z. Annals of Nuclear Energy, 2005, 32, (10), 1081–1099

06/00408 A novel channel selection method for CANDUrefuelling based on the BPANN and GA techniques: Huo, X. and Xie, Z. Annals of Nuclear Energy, 2005, 32, (10), 1081–1099

06/00075 Collision, scattering and absorption differential cross-sections in double-photon Compton scattering: Dewan, R. et al. Annals of Nuclear Energy, 2005, 32, (9), 1008–1022

06/00075 Collision, scattering and absorption differential cross-sections in double-photon Compton scattering: Dewan, R. et al. Annals of Nuclear Energy, 2005, 32, (9), 1008–1022

05/00438 A Galerkin approach to the boundary element-response matrix method for the multigroup neutron diffusion equations: Maiani, M. and Montagnini, B. Annals of Nuclear Energy, 2004, 31, (13), 1447–1475

05/00438 A Galerkin approach to the boundary element-response matrix method for the multigroup neutron diffusion equations: Maiani, M. and Montagnini, B. Annals of Nuclear Energy, 2004, 31, (13), 1447–1475

05/00102 Measurement and analysis of decay heat of fast reactor spent MOX fuel: Maeda, S. et al. Annals of Nuclear Energy, 2004, 31, (10), 1119–1133

05/00102 Measurement and analysis of decay heat of fast reactor spent MOX fuel: Maeda, S. et al. Annals of Nuclear Energy, 2004, 31, (10), 1119–1133

05/00493 Transient and stability analysis in single-phase natural circulation: Mousavian, S. K. et al. Annals of Nuclear Energy, 2004, 31, (10), 1177–1198

05/00493 Transient and stability analysis in single-phase natural circulation: Mousavian, S. K. et al. Annals of Nuclear Energy, 2004, 31, (10), 1177–1198

05/00447 Cell homogenization methods for pin-by-pin core calculations tested in slab geometry: Yamamoto, A. et al. Annals of Nuclear Energy, 2004, 31, (8), 825–847

05/00447 Cell homogenization methods for pin-by-pin core calculations tested in slab geometry: Yamamoto, A. et al. Annals of Nuclear Energy, 2004, 31, (8), 825–847

05/00449 Computer codes for spectrum average cross section calculations: Caldeira, A. D. and Carlson, B. V. Annals of Nuclear Energy, 2004, 31, (9), 1069–1072

05/00449 Computer codes for spectrum average cross section calculations: Caldeira, A. D. and Carlson, B. V. Annals of Nuclear Energy, 2004, 31, (9), 1069–1072

05/00090 Analysis of a PWR core baffle considering irradiation induced creep: Altstadt, E. et al. Annals of Nuclear Energy, 2004, 31, (7), 723–736

05/00090 Analysis of a PWR core baffle considering irradiation induced creep: Altstadt, E. et al. Annals of Nuclear Energy, 2004, 31, (7), 723–736

05/00306 A soft-computing based classification procedure for the identification of transients in the steam generator of a pressurized water reactor: Marseguerra, M. et al. Annals of Nuclear Energy, 2004, 31, (13), 1429–1446

05/00306 A soft-computing based classification procedure for the identification of transients in the steam generator of a pressurized water reactor: Marseguerra, M. et al. Annals of Nuclear Energy, 2004, 31, (13), 1429–1446

05/00112 Validation study of the cell code WIMS-D and a 69 group library based on JENDL-3.2: Rahman, M. et al. Annals of Nuclear Energy, 2004, 31, (12), 1357–1383

05/00112 Validation study of the cell code WIMS-D and a 69 group library based on JENDL-3.2: Rahman, M. et al. Annals of Nuclear Energy, 2004, 31, (12), 1357–1383

05/00488 Studies on equation of state of high temperature nuclear materials: Joseph, M. et al. Annals of Nuclear Energy, 2004, 31, (10), 1163–1175

05/00488 Studies on equation of state of high temperature nuclear materials: Joseph, M. et al. Annals of Nuclear Energy, 2004, 31, (10), 1163–1175

05/00097 Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code: Hamidouche, T. et al. Annals of Nuclear Energy, 2004, 31, (12), 1385–1402

05/00097 Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code: Hamidouche, T. et al. Annals of Nuclear Energy, 2004, 31, (12), 1385–1402

05/00107 Shield structure optimisation studies for the west beam port of the KAMINI reactor: Sunny, C. S. and Subbaiah, K. V. Annals of Nuclear Energy, 2004, 31, (12), 1403–1413

05/00107 Shield structure optimisation studies for the west beam port of the KAMINI reactor: Sunny, C. S. and Subbaiah, K. V. Annals of Nuclear Energy, 2004, 31, (12), 1403–1413

05/00117 Identifying and training non-technical skills of nuclear emergency response teams: Crichton, M. T. and Flin, R. Annals of Nuclear Energy, 2004, 31, (12), 1317–1330

Maps of local plasma emissivity of TJ-II plasmas are determined using three-array cameras of silicon photodiodes (AXUV type from IRD). They have assigned the top and side ports of the same sector of the vacuum vessel. Each array consists of 20 unfiltered detectors. The signals from each of these detectors are the inputs to an iterative algorithm of tomographic reconstruction. Currently, these signals are acquired by a PXI standard system at approximately 50 kS/s, with 12 bits of resolution and are stored for off-line processing. A 0.5 s discharge generates 3 Mbytes of raw data. The algorithm's load exceeds the CPU capacity of the PXI system's controller in a continuous mode, making unfeasible to process the samples in parallel with their acquisition in a PXI standard system. A new architecture model has been developed, making possible to add one or several processing cards to a standard PXI system. With this model, it is possible to define how to distribute, in real-time, the data from all acquired signals in the system among the processing cards and the PXI controller. This way, by distributing the data processing among the system controller and two processing cards, the data processing can be done in parallel with the acquisition. Hence, this system configuration would be able to measure even in long pulse devices.

05/00103 Neutronics analyses of natural uranium fueled, light water cooled, heavy water moderated and graphite reflected nuclear reactors: Khan, M. J. et al. Annals of Nuclear Energy, 2004, 31, (12), 1331–1356

05/00103 Neutronics analyses of natural uranium fueled, light water cooled, heavy water moderated and graphite reflected nuclear reactors: Khan, M. J. et al. Annals of Nuclear Energy, 2004, 31, (12), 1331–1356

05/00471 Monte Carlo importance sampling optimization for system reliability applications: Campioni, L. and Vestrucci, P. Annals of Nuclear Energy, 2004, 31, (9), 1005–1025

Reduced activation ferritic/martensitic steels (RAFM steels) are presently considered as the primary structural materials for a demonstration (DEMO) fusion plant and the first fusion power reactors because of their attractive properties. Studies on various properties of China low activation martensitic steel (CLAM) are underway. The activation level of CLAM steel was calculated with the widely used inventory code FISPACT with the latest data library FENDL/A-2 based on the first wall (FW) neutron spectrum of the fusion-driven subcritical system (FDS) from the Monte Carlo transport code MCNP/4C calculation with FENDL-2 data library. The results were compared with the activation levels of other RAFM steels, such as EUROFER97, F82H, JLF-1 and 9Cr–2WVTa etc., under the same irradiation conditions. Furthermore, the dominant nuclides to γ-ray dose rate of CLAM steel were analyzed. The required control levels of impurities in CLAM steel will soon be implemented based on the hands-on and remote recycling dose rate limits.

04/02767 Development of core fuel management codesystem for CANDU reactor based on coupled neutronics and thermal-hydraulic advanced nodal method: Huo, X. et al. Annals of Nuclear Energy, 2004, 31, (10), 1083–1100

04/02767 Development of core fuel management codesystem for CANDU reactor based on coupled neutronics and thermal-hydraulic advanced nodal method: Huo, X. et al. Annals of Nuclear Energy, 2004, 31, (10), 1083–1100

04/03025 Energy and chemical composition dependence of mass attenuation coefficients of building materials: Singh, C. et al. Annals of Nuclear Energy, 2004, 31, (10), 1199–1205

04/03025 Energy and chemical composition dependence of mass attenuation coefficients of building materials: Singh, C. et al. Annals of Nuclear Energy, 2004, 31, (10), 1199–1205

04/03147 The photon attenuation coefficients of barite,marble and limra: Akkurt, I. et al. Annals of Nuclear Energy, 2004, 31, (5), 577–582

04/03147 The photon attenuation coefficients of barite,marble and limra: Akkurt, I. et al. Annals of Nuclear Energy, 2004, 31, (5), 577–582