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Sample records for evaluated nuclear parameter

  1. Progress on chinese evaluated nuclear parameter library: Pt.5

    Energy Technology Data Exchange (ETDEWEB)

    Zongdi, Su; Zhongfu, Huang; Jianfeng, Liu [and others

    1996-06-01

    The progress on chinese evaluated nuclear parameter library (v) was introduced. Six sub-libraries, MCC, DLS, NLD, GDP, FBP and OMP, including their data files and management-retrieval code systems have all been finished. All six sub-libraries have been used in nuclear model calculations, nuclear data evaluations and other fields in China. The applied results show that our evaluated nuclear parameter library is satisfactory and convenient.

  2. Progress on Chinese evaluated nuclear parameter library (CENPL) (II)

    International Nuclear Information System (INIS)

    Su Zhongdi; Ge Zhigang; Zhou Chunmei

    1993-01-01

    CENPL collected, evaluated and compiled nuclear basic constants and model parameters. CENPL-1 contain six sub-libraries, they are: (1) Atomic masses and characteristic constants for nuclear ground states; (2) discrete level schemes and branch ratios of γ decay; (3) level density parameters; (4) giant dipole resonance parameters for γ-ray strength function (5) fission barrier parameter; (6) optical model parameters. Their progresses are introduced

  3. Progress on Chinese evaluated nuclear parameters library (CENPL). Pt. 3

    International Nuclear Information System (INIS)

    Su Zongdi; Ge Zhigang; Zhou Chunmei

    1994-01-01

    The progress on Chinese evaluated nuclear parameters library (CENPL) is introduced. The setting up work of each sub-library of CENPL has got some new progresses at the past period. These sub-libraries are atomic mass and characteristic constant for nuclear ground state sub-library, discrete level scheme and batch ratio of γ decay sub-library, level density parameter sub-library, giant dipole resonance parameter for γ-ray strength function sub-library and optical model parameter sub-library

  4. Nuclear criticality safety parameter evaluation for uranium metallic alloy

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, Andrea; Abe, Alfredo, E-mail: andreasdpz@hotmail.com, E-mail: abye@uol.com.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Centro de Energia Nuclear

    2013-07-01

    Nuclear criticality safety during fuel fabrication process, transport and storage of fissile and fissionable materials requires criticality safety analysis. Normally the analysis involves computer calculations and safety parameters determination. There are many different Criticality Safety Handbooks where such safety parameters for several different fissile mixtures are presented. The handbooks have been published to provide data and safety principles for the design, safety evaluation and licensing of operations, transport and storage of fissile and fissionable materials. The data often comprise not only critical values, but also subcritical limits and safe parameters obtained for specific conditions using criticality safety calculation codes such as SCALE system. Although many data are available for different fissile and fissionable materials, compounds, mixtures, different enrichment level, there are a lack of information regarding a uranium metal alloy, specifically UMo and UNbZr. Nowadays uranium metal alloy as fuel have been investigated under RERTR program as possible candidate to became a new fuel for research reactor due to high density. This work aim to evaluate a set of criticality safety parameters for uranium metal alloy using SCALE system and MCNP Monte Carlo code. (author)

  5. American National Standard: guidelines for evaluating site-related geotechnical parameters at nuclear power sites

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    This standard presents guidelines for evaluating site-related geotechnical parameters for nuclear power sites. Aspects considered include geology, ground water, foundation engineering, and earthwork engineering. These guidelines identify the basic geotechnical parameters to be considered in site evaluation, and in the design, construction, and performance of foundations and earthwork aspects for nuclear power plants. Also included are tabulations of typical field and laboratory investigative methods useful in identifying geotechnical parameters. Those areas where interrelationships with other standards may exist are indicated

  6. Calculation of the neutron activation parameters from recently evaluated nuclear data

    International Nuclear Information System (INIS)

    Lopez Aldama, Daniel; Diaz Martinez, Nereida C.

    1999-01-01

    Neutron Activation Analysis (NAA) requires the values for nuclear data such as the 2200 m/s cross section so, the resonance integral I0, the parameter Q0 and the well-known Westcott factors. The availability of recently evaluated nuclear data libraries as the ENDF/B-VI Rev. 5, JEF 2.2, CENDL-2.1 and JENDL-3.2, makes possible to derive the above quantities from the basic nuclear data. It could be very helpful for those NAA parameters, which are unknown or difficult to measure accurately. The procedure to compute the NAA parameters includes the processing of the evaluated nuclear data and the calculation of each parameter directly from its definition. The evaluated nuclear data libraries ENDF/B-VI Rev. 5 and JENDL 3.2 were selected as the main sources of basic nuclear data. The ENDF pre-processing codes were used for processing the source evaluated data and a modified version of the INTER code was applied to calculate the required NAA integrals. The NAA parameters were computed for more than 30 important isotopes. The obtained results were compared with experimental values whenever possible

  7. Nuclear data project in Korea and resonance parameter evaluation of fission products

    International Nuclear Information System (INIS)

    Chang, Jonghwa; Oh, Soo-Youl

    2000-01-01

    Nuclear data activities in the fields of evaluation, processing, measurement, and service in Korea are presented in this paper. As one of the current activities, the neutron resonance parameters for stable or long-lived nineteen fission products have been evaluated and the results are presented here. (author)

  8. Bonderenko self-shielded cross sections and multiband parameters derived from the LLL Evaluated-Nuclear-Data Library (ENDL)

    International Nuclear Information System (INIS)

    Cullen, D.E.

    1978-01-01

    Bonderenko self-shielded cross sections and multiband parameters from the Lawrence Livermore Laboratory Evaluated-Nuclear-Data Library (ENDL) as of July 4, 1978 are presented. These data include total, elastic, capture, and fission cross sections in the TART 175 group structure. Multiband parameters are listed. Bonderenko self-shielded cross section and the multiband parameters are presented on microfiche

  9. Evaluation of water quality parameters and associated environmental impact at nuclear power plant sites

    International Nuclear Information System (INIS)

    Joshi, M.L.; Hegde, A.G.

    2005-01-01

    The Nuclear Power Plants use a large quantity of water for the purpose of cooling the turbine condenser. The heated effluents are discharged to aquatic environment by means of once through cooling wherever large water bodies like seacoast or fresh water reservoir are available. The quality of water bodies are important for the growth and biodiversity of aquatic organisms. Several environmental factors like Temperature pH, Dissolved Oxygen have a bearing on the life cycle of aquatic organisms. The paper describes the evaluation of water quality parameters at the two typical sites one on the sea coast (Tarapur) and other at inland site Kaiga and discusses the environmental impact due to discharge to aquatic environment. It is found that the environmental impacts due to both heated effluents and radioactivity are insignificant. The water quality parameters are found to be well within the prescribed standards. (author)

  10. Radiation portal evaluation parameters

    International Nuclear Information System (INIS)

    York, R.L.

    1998-01-01

    The detection of the unauthorized movement of radioactive materials is one of the most effective nonproliferation measures. Automatic special nuclear material (SNM) portal monitors are designed to detect this unauthorized movement and are an important part of the safeguard systems at US nuclear facilities. SNM portals differ from contamination monitors because they are designed to have high sensitivity for the low energy gamma-rays associated with highly enriched uranium (HEU) and plutonium. These instruments are now being installed at international borders to prevent the spread of radioactive contamination an SNM. In this paper the parameters important to evaluating radiation portal monitors are discussed. (author)

  11. Evaluation of selected parameters on exposure rates in Westinghouse designed nuclear power plants

    International Nuclear Information System (INIS)

    Bergmann, C.A.

    1989-01-01

    During the past ten years, Westinghouse under EPRI contract and independently, has performed research and evaluation of plant data to define the trends of ex-core component exposure rates and the effects of various parameters on the exposure rates. The effects of the parameters were evaluated using comparative analyses or empirical techniques. This paper updates the information presented at the Fourth Bournemouth Conference and the conclusions obtained from the effects of selected parameters namely, coolant chemistry, physical changes, use of enriched boric acid, and cobalt input on plant exposure rates. The trends of exposure rates and relationship to doses is also presented. (author)

  12. ZZ-CENPL, Chinese Evaluated Nuclear Parameter Library. ZZ CENPL-DLS, Discrete Level Schemes and Gamma Branching Ratios Library; ZZ CENPL-FBP, Fission Barrier Parameter Library; ZZ CENPL-GDRP, Giant Dipole Resonance Parameter Library; ZZ CENPL-NLD, Nuclear Level Density Parameter Library; ZZ CENPL-MCC, Nuclear Ground State Atomic Masses Library; ZZ CENPL-OMP, Optical Model Parameter Library

    International Nuclear Information System (INIS)

    Su Zongdi

    1995-01-01

    Description of program or function: CENPL - GDRP (Giant Dipole Resonance Parameters for Gamma-Ray): - Format: special format described in documentation; - Nuclides: V, Mn, Co, Ni, Cu, Zn, Ga, Ge, As, Se, Rb, Sr, Y, Zr, Nb, Mo, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Cs, Ba, La, Ce, Pr, Nd, Sm, Eu, Gd, Tb, Ho, Er, Lu, Ta, W, Re, Os, Ir, Pt, Au, Hg, Pb, Bi, Th, U, Np, Pu. - Origin: Experimental values offered by S.S. Dietrich and B.L. Berman. CENPL - FBP (Fission Barrier Parameter Sub-Library): - Format: special format described in documentation; - Nuclides: (1) 51 nuclei region from Th-230 to Cf-255, (2) 46 nuclei region from Th-229 to Cf-253, (3) 24 nuclei region from Pa-232 to Cf-253; - Origin: (1) Lynn, (2) Analysis of experimental data by Back et al., (3) Ohsawa. CENPL - DLS (Discrete level scheme and branch ratio of gamma decay: - Format: Special format described in documentation; - Origin: ENSDF - BNL. CENPL - NLD (Nuclear Level Density): - Format: Special format described in documentation; - Origin: Huang Zhongfu et al. CENPL - OMP (Optical model parameter sub-library): - Format: special format described in documentation ; - Origin: CENDL, ENDF/B-VI, JENDL-3. CENPL - MC (I) and (II) (Atomic masses and characteristic constants for nuclear ground states) : - Format: Brief table format; - Nuclides: 4760 nuclides ranging from Z=0 A=1 to Z=122 A=318. - Origin: Experimental data and systematic results evaluated by Wapstra, theoretical results calculated by Moller, ENSDF - BNL and Nuclear Wallet Cards. CENPL contains the following six sub-libraries: 1. Atomic Masses and Characteristic Constants for nuclear ground states (MCC). This data consists of calculated and in most cases also measured mass excesses, atomic masses, total binding energies, spins, parities, and half-lives of nuclear ground states, abundances, etc. for 4800 nuclides. 2. Discrete Level Schemes and branching ratios of gamma decay (DLS). The data on nuclear discrete levels are based on the Evaluated

  13. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    International Nuclear Information System (INIS)

    Uddin, M.N.; Sarker, M.M.; Khan, M.J.H.; Islam, S.M.A.

    2010-01-01

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, k eff and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  14. Evaluation of nuclear parameters measurements realized during the Angra-1 reactor start-up tests and the theoretical previsions of these parameters

    International Nuclear Information System (INIS)

    Fernandes, V.B.; Ponzoni Filho, P.; Perrotta, J.A.; Silva Ipojuca, T. da

    1982-01-01

    A summary of measuring techniques and the results of the follow nuclear parameters, are presented: a) reactivity of various control bank; b) capacity of reactor shutdown; c) critical concentrations of soluble boron for various core configurations; d) reactivity isothermal coefficients; e) power mapping; f) power reactivity coefficients. (E.G.) [pt

  15. Nuclear model parameter testing for nuclear data evaluation (Reference Input Parameter Library: Phase II). Summary report of the third research co-ordination meeting

    International Nuclear Information System (INIS)

    Herman, M.

    2002-04-01

    This report summarises the results and recommendations of the third Research Co-ordination Meeting on improving and testing the Reference Input Parameter Library: Phase II. A primary aim of the meeting was to review the achievements of the CRP, to assess the testing of the library and to approve the final contents. Actions were approved that will result in completion of the file and a draft report by the end of February 2002. Full release of the library is scheduled for July 2002. (author)

  16. Nuclear model parameter testing for nuclear data evaluation (Reference Input Parameter Library: Phase II). Summary report of the second research co-ordination meeting

    International Nuclear Information System (INIS)

    Herman, M.

    2000-09-01

    This report summarizes the results and recommendations of the Second Research Coordination Meeting on Testing and Improvement of the Reference Input Parameter Library: Phase II. A primary aim of this meeting was to review progress in the CRP work, to review results of testing the library, to establish the RIPL-2 format and to decide on the contents of the library. The actions were agreed with an aim to complete the project by the end of 2001. Separate abstracts were prepared for 10 individual papers

  17. Stereological estimation of nuclear volume and other quantitative histopathological parameters in the prognostic evaluation of supraglottic laryngeal squamous cell carcinoma

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Bennedbaek, O; Pilgaard, J

    1989-01-01

    The aim of this study was to investigate various approaches to the grading of malignancy in pre-treatment biopsies from patients with supraglottic laryngeal squamous cell carcinoma. The prospects of objective malignancy grading based on stereological estimation of the volume-weighted mean nuclear...... observers of the latter was poor in the material which consisted of 35 biopsy specimens. Unbiased estimates of nuclear Vv were on the average 385 microns3 (CV = 0.44), with more than 90% of the associated variance attributable to differences in nuclear Vv among individual lesions. Nuclear Vv was positively....... None of the investigated categorical and quantitative parameters (cutoff points = means) reached the level of significance with respect to prognostic value. However, nuclear Vv showed the best information concerning survival (2p = 0.08), and this estimator offers optimal features for objective...

  18. Computation code TEP 1 for automated evaluation of technical and economic parameters of operation of WWER-440 nuclear power plant units

    International Nuclear Information System (INIS)

    Zadrazil, J.; Cvan, M.; Strimelsky, V.

    1987-01-01

    The TEP 1 program is used for automated evaluation of the technical and economic parameters of nuclear power plant units with WWER-440 reactors. This is an application program developed by the Research Institute for Nuclear Power Plants in Jaslovske Bohunice for the KOMPLEX-URAN 2M information system, delivered by the USSR to the V-2 nuclear power plants in Jaslovske Bohunice and in Dukovany. The TEP 1 program is written in FORTRAN IV and its operation has two parts. First the evaluation of technical and economic parameters of operation for a calculation interval of 10 mins and second, the control of the calculation procedure, follow-up on input data, determination of technical and economic parameters for a lengthy time interval, and data printout and storage. The TEP 1 program was tested at the first unit of the V-2 power plant and no serious faults appeared in the process of the evaluation of technical and economic parameters. A modification of the TEP 1 programme for the Dukovany nuclear power plant is now being tested on the first unit of the plant. (Z.M.)

  19. Validation of CENDL and JEFF evaluated nuclear data files for TRIGA calculations through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors

    International Nuclear Information System (INIS)

    Uddin, M.N.; Sarker, M.M.; Khan, M.J.H.; Islam, S.M.A.

    2009-01-01

    The aim of this paper is to present the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through the analysis of the integral parameters of TRX and BAPL benchmark lattices of thermal reactors for neutronics analysis of TRIGA Mark-II Research Reactor at AERE, Bangladesh. In this process, the 69-group cross-section library for lattice code WIMS was generated using the basic evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 with the help of nuclear data processing code NJOY99.0. Integral measurements on the thermal reactor lattices TRX-1, TRX-2, BAPL-UO 2 -1, BAPL-UO 2 -2 and BAPL-UO 2 -3 served as standard benchmarks for testing nuclear data files and have also been selected for this analysis. The integral parameters of the said lattices were calculated using the lattice transport code WIMSD-5B based on the generated 69-group cross-section library. The calculated integral parameters were compared to the measured values as well as the results of Monte Carlo Code MCNP. It was found that in most cases, the values of integral parameters show a good agreement with the experiment and MCNP results. Besides, the group constants in WIMS format for the isotopes U-235 and U-238 between two data files have been compared using WIMS library utility code WILLIE and it was found that the group constants are identical with very insignificant difference. Therefore, this analysis reflects the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through benchmarking the integral parameters of TRX and BAPL lattices and can also be essential to implement further neutronic analysis of TRIGA Mark-II research reactor at AERE, Dhaka, Bangladesh.

  20. Stereological estimation of nuclear volume and other quantitative histopathological parameters in the prognostic evaluation of supraglottic laryngeal squamous cell carcinoma

    DEFF Research Database (Denmark)

    Sørensen, Flemming Brandt; Bennedbaek, O; Pilgaard, J

    1989-01-01

    The aim of this study was to investigate various approaches to the grading of malignancy in pre-treatment biopsies from patients with supraglottic laryngeal squamous cell carcinoma. The prospects of objective malignancy grading based on stereological estimation of the volume-weighted mean nuclear...... volume, nuclear Vv, and nuclear volume fraction, Vv(nuc/tis), along with morphometrical 2-dimensional estimation of nuclear density index, NI, and mitotic activity index, MI, were investigated and compared with the current morphological, multifactorial grading system. The reproducibility among two...... observers of the latter was poor in the material which consisted of 35 biopsy specimens. Unbiased estimates of nuclear Vv were on the average 385 microns3 (CV = 0.44), with more than 90% of the associated variance attributable to differences in nuclear Vv among individual lesions. Nuclear Vv was positively...

  1. Evaluation of the Cerro Solo nuclear ore, province of Chubut. On the economic parameters of the deposit. Pt. 3

    International Nuclear Information System (INIS)

    Navarra, P.R.; Sardin, P.G.; Urquiza, L.; Bernal, G.J.; Guzman Lobos, D.

    1993-01-01

    Preliminary results of the resources estimation carried out in the Cerro Solo uranium ore deposit, located in the Chubut Province, 1900 km SW from Buenos Aires and 380 Km W from Trelew, presented in tonnes of uranium recoverable at costs up to U$S 80/kgU, are as follows: a) Reasonable assured resources (indicated): 800 tU; b) Estimates Additional Resources (inferred): 2200 tU. Economic evaluation at the order-of-magnitude level, performed using the grade-tonnage model of the deposit, resulted a useful tool in the different stages of the project to identify the influence of technical parameters on the potential profitability. Research about feasibility of in-situ leaching method of exploitation for this deposit introduces an interesting alternative for future uranium production in the country. (Author)

  2. Validation study of SRAC2006 code system based on evaluated nuclear data libraries for TRIGA calculations by benchmarking integral parameters of TRX and BAPL lattices of thermal reactors

    International Nuclear Information System (INIS)

    Khan, M.J.H.; Sarker, M.M.; Islam, S.M.A.

    2013-01-01

    Highlights: ► To validate the SRAC2006 code system for TRIGA neutronics calculations. ► TRX and BAPL lattices are treated as standard benchmarks for this purpose. ► To compare the calculated results with experiment as well as MCNP values in this study. ► The study demonstrates a good agreement with the experiment and the MCNP results. ► Thus, this analysis reflects the validation study of the SRAC2006 code system. - Abstract: The goal of this study is to present the validation study of the SRAC2006 code system based on evaluated nuclear data libraries ENDF/B-VII.0 and JENDL-3.3 for neutronics analysis of TRIGA Mark-II Research Reactor at AERE, Bangladesh. This study is achieved through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors. In integral measurements, the thermal reactor lattices TRX-1, TRX-2, BAPL-UO 2 -1, BAPL-UO 2 -2 and BAPL-UO 2 -3 are treated as standard benchmarks for validating/testing the SRAC2006 code system as well as nuclear data libraries. The integral parameters of the said lattices are calculated using the collision probability transport code PIJ of the SRAC2006 code system at room temperature 20 °C based on the above libraries. The calculated integral parameters are compared to the measured values as well as the MCNP values based on the Chinese evaluated nuclear data library CENDL-3.0. It was found that in most cases, the values of integral parameters demonstrate a good agreement with the experiment and the MCNP results. In addition, the group constants in SRAC format for TRX and BAPL lattices in fast and thermal energy range respectively are compared between the above libraries and it was found that the group constants are identical with very insignificant difference. Therefore, this analysis reflects the validation study of the SRAC2006 code system based on evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 and can also be essential to implement further neutronics calculations

  3. Computational Analysis of Nuclear Safety Parameters of 3 MW TRIGA Mark-II Research Reactor Based on Evaluated Nuclear Data Libraries JENDL-3.3 and ENDF/B-VII.0

    International Nuclear Information System (INIS)

    Khan, Jahirul Haque

    2013-01-01

    The objective of this study is to explain the main nuclear safety parameters of 3 MW TRIGA Mark-II Research Reactor at AERE, Savar, Dhaka, Bangladesh from the viewpoint of reactor safety and also reactor operator. The most important nuclear reactor physics safety parameters are power distribution, power peaking factors, shutdown margin, control rod worth, excess reactivity and fuel temperature reactivity coefficient. These parameters are calculated using the chain of the computer codes the SRAC-PIJ for cell calculation based on neutron transport theory and the SRAC-CITATION for core calculation based on neutron diffusion equation. To achieve this objective the TRIGA model is developed by the 3-D diffusion code SRAC-CITATION based on the group constants that come from the collision probability transport code SRAC-PIJ. In this study the evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 are used. The calculated most important reactor physics parameters are compared to the safety analysis report (SAR) values as well as earlier published MCNP results (numerically benchmark). It was found that the calculated results show a good agreement between the said libraries. Besides, in most cases the calculated results reveal a reasonable agreement with the SAR values (by General Atomic) as well as the MCNP results. In addition, this analysis can be used as the inputs for thermal-hydraulic calculations of the TRIGA fresh core in the steady state and pulse mode operation. Because of power peaking factors, power distributions and temperature reactivity coefficients are the most important reactor safety parameters for normal operation and transient safety analysis in research as well as in power reactors. They form the basis for technical specifications and limitations for reactor operation such as loading pattern limitations for pulse operation (in TRIGA). Therefore, this analysis will be very important to develop the nuclear safety parameters data of 3 MW TRIGA Mark

  4. Mass and Inertia Parameters for Nuclear Fission

    International Nuclear Information System (INIS)

    Damgaard, J.; Pauli, H.C.; Strutinsky, V.M.; Wong, C.Y.; Brack, M.; Stenholm-Jensen, A.

    1969-01-01

    The effective mass parameter and the moments of inertia for a deformed nucleus are evaluated using the cranking-model formalism. Special attention is paid to the dependence of these quantities on the intrinsic structure, which may arise due to shells in deformed nuclei. It is found that these inertial parameters are very much influenced by the shells present. The effective-mass parameter, which appears in an important way in the theory of spontaneous fission, fluctuates in the same manner as the shell-energy corrections. Its values at the fission barrier are up to two or three times larger than those at the equilibrium minima. This correlation comes about because for the effective mass the change in the local density of single-particle states is very important, much more so than the change in the pairing correlation. The moments of inertia which enter in the theory of angular anisotropy of fission fragments, also fluctuate as a function of the deformation. At low temperatures, the fluctuation is large and shows a distinct but more complicated correlation with the shells. At high temperatures, the moments of inertia fluctuate with a smaller amplitude about the rigid-body value in correlation with the energy-shell corrections. For the first-and second barriers, the rigid-body values are essentially reached at a nuclear temperature of 0.8 to 1.0 MeV. (author)

  5. Evaluated Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    Oblozinsky, P.; Oblozinsky,P.; Herman,M.; Mughabghab,S.F.

    2010-10-01

    This chapter describes the current status of evaluated nuclear data for nuclear technology applications. We start with evaluation procedures for neutron-induced reactions focusing on incident energies from the thermal energy up to 20 MeV, though higher energies are also mentioned. This is followed by examining the status of evaluated neutron data for actinides that play dominant role in most of the applications, followed by coolants/moderators, structural materials and fission products. We then discuss neutron covariance data that characterize uncertainties and correlations. We explain how modern nuclear evaluated data libraries are validated against an extensive set of integral benchmark experiments. Afterwards, we briefly examine other data of importance for nuclear technology, including fission yields, thermal neutron scattering and decay data. A description of three major evaluated nuclear data libraries is provided, including the latest version of the US library ENDF/B-VII.0, European JEFF-3.1 and Japanese JENDL-3.3. A brief introduction is made to current web retrieval systems that allow easy access to a vast amount of up-to-date evaluated nuclear data for nuclear technology applications.

  6. Evaluated nuclear data library

    International Nuclear Information System (INIS)

    Howerton, R.J.; Dye, R.E.; Perkins, S.T.

    1981-01-01

    The Lawrence Livermore National Laboratory (LLNL) collection of evaluated data for neutron-, photon-, and charged-particle-induced reactions is maintained in a computer-oriented system. In this report we recount the history of Evaluated Nuclear Data Library, describe the methods of evaluation, and give examples of input and output representation of the data

  7. Systematics of nuclear level density parameters

    International Nuclear Information System (INIS)

    Bucurescu, Dorel; Egidy, Till von

    2005-01-01

    The level density parameters for the back-shifted Fermi gas (both without and with energy-dependent level density parameter) and the constant temperature models have been determined for 310 nuclei between 18 F and 251 Cf by fitting the complete level schemes at low excitation energies and the s-wave neutron resonance spacings at the neutron binding energies. Simple formulae are proposed for the description of the two parameters of each of these models, which involve only quantities available from the mass tables. These formulae may constitute a reliable tool for extrapolating to nuclei far from stability, where nuclear level densities cannot be measured

  8. Nuclear Data Parameter Adjustment BNL-INL

    International Nuclear Information System (INIS)

    Palmiotti, G.; Hoblit, S.; Herman, M.; Nobre, G.P.A.; Palumbo, A.; Hiruta, H.; Salvatores, M.

    2013-01-01

    This presentation reports on the consistent adjustment of nuclear data parameters performed within a BNL-INL collaboration. The main advantage compared to the classical adjustment of multigroup constants is to provide final nuclear data constrained by the nuclear reaction theory and consistent with both differential and integral measurements. The feasibility of a single-isotope assimilation was tested on a few priority materials ( 23 Na, 56 Fe, 105 Pd, 235,238 U, 239 Pu) using a selection of clean integral experiments. The multi-isotope assimilation is under study for the Big-3 ( 235,238 U, 239 Pu). This work shows that a consistent assimilation is feasible, but there are pitfalls to avoid (e.g. non-linearity, cross section fluctuations) and prerequisites (e.g. realistic covariances, good prior, realistic weighting of differential and integral experiments). Finally, only all experimental information combined with the state of the art modelling may provide a 'right' answer

  9. The evaluation of set of criticality parameters using scale system

    International Nuclear Information System (INIS)

    Abe, Alfredo; Sanchez, Andrea; Yamaguchi, Mistuo

    2009-01-01

    In evaluating the criticality safety of the nuclear fuel facility, it is important to apply a consistent methodology, which consider every aspects concerning various types of criticality parameters. Usually, the critical parameters are compiled and arranged into handbooks, and these handbooks are based on experience with nuclear facilities, experimental data from criticality safety research facilities, and theoretical studies performed using numerical simulations. Most of criticality safety evaluation can be addressed using the criticality parameters data directly from handbook, but some critical parameters for a specific chemical mixtures and/or enrichment are not be available. Consequently, not available parameters has to be evaluated. This work present the methodology to evaluate a set of critical parameters using SCALE system for various types of mixtures present at nuclear fuel cycle facilities for two different level of enrichment, the results are verified in the independent calculation using MCNP Monte Carlo Code. (author)

  10. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries ENDF/B-VII.0 and JENDL-3.3

    International Nuclear Information System (INIS)

    Altaf, M.H.; Badrun, N.H.; Chowdhury, M.T.

    2015-01-01

    Highlights: • SRAC-PIJ code and SRAC-CITATION have been utilized to model the core. • Most of the simulated results show no significant differences with references. • Thermal peak flux varies a bit due to up condition of TRIGA. • ENDF/B-VII.0 and JENDL-3.3 libraries perform well for neutronics analysis of TRIGA. - Abstract: Important kinetic parameters such as effective multiplication factor, k eff , excess reactivity, neutron flux and power distribution, and power peaking factors of TRIGA Mark II research reactor in Bangladesh have been calculated using the comprehensive neutronics calculation code system SRAC 2006 with the evaluated nuclear data libraries ENDF/B-VII.0 and JENDL-3.3. In the code system, PIJ code was employed to obtain cross section of the core cells, followed by the integral calculation of neutronic parameters of the reactor conducted by CITATION code. All the analyses were performed using the 7-group macroscopic cross section library. Results were compared to the experimental data, the safety analysis report (SAR) of the reactor provided by General Atomic as well as to the simulated values by numerically benchmarked MCNP4C, WIMS-CITATION and SRAC-CITATION codes. The maximum power densities at the hot spot were found to be 169.7 W/cc and 170.1 W/cc for data libraries ENDF/B-VII.0 and JENDL-3.3, respectively. Similarly, the total peaking factors based on ENDF/B-VII.0 and JENDL-3.3 were calculated as 5.68 and 5.70, respectively, which were compared to the original SAR value of 5.63, as well as to MCNP4C, WIMS-CITATION and SRAC-CITATION results. It was found in most cases that the calculated results demonstrate a good agreement with our experiments and published works. Therefore, this analysis benchmarks the code system and will be helpful to enhance further neutronics and thermal hydraulics study of the reactor

  11. Statistical estimation of nuclear reactor dynamic parameters

    International Nuclear Information System (INIS)

    Cummins, J.D.

    1962-02-01

    This report discusses the study of the noise in nuclear reactors and associated power plant. The report is divided into three distinct parts. In the first part parameters which influence the dynamic behaviour of some reactors will be specified and their effect on dynamic performance described. Methods of estimating dynamic parameters using statistical signals will be described in detail together with descriptions of the usefulness of the results, the accuracy and related topics. Some experiments which have been and which might be performed on nuclear reactors will be described. In the second part of the report a digital computer programme will be described. The computer programme derives the correlation functions and the spectra of signals. The programme will compute the frequency response both gain and phase for physical items of plant for which simultaneous recordings of input and output signal variations have been made. Estimations of the accuracy of the correlation functions and the spectra may be computed using the programme and the amplitude distribution of signals may also b computed. The programme is written in autocode for the Ferranti Mercury computer. In the third part of the report a practical example of the use of the method and the digital programme is presented. In order to eliminate difficulties of interpretation a very simple plant model was chosen i.e. a simple first order lag. Several interesting properties of statistical signals were measured and will be discussed. (author)

  12. Atomic and nuclear parameters of single electron capture decaying nuclides

    International Nuclear Information System (INIS)

    Grau, A.

    1981-01-01

    Atomic and nuclear parameters of the following nuclides which decay by electron capture have been calculated: 37 A r, 41 C a, 49 V , 53 M n, 55 F e,59 N i, 68Ge,82 S r, 97 T c, 118 T e, 131 C s, 137 L a, 140 N d, 157 T b, 165 E r, 193 p t, 194 H g, and 205 P h The evaluation rules are included in the first part of the paper. The values and the associated uncertainties of the following parameters have been tabulated: decay energy, electron capture probabilities, fluorescence yield, electron emission and X-ray emission. (Author) 27 refs

  13. Evaluating nuclear communications

    International Nuclear Information System (INIS)

    Middlemiss, Nigel

    1998-01-01

    plant, and how messages on nuclear safety, economics, waste and exports were accepted and rejected by the media; - how large the payback can be from proactive - not just reactive - media work, as evidenced in an analysis for an industrial group involved in North Sea oil plant decommissioning. A demonstration will be given showing the parameters that can be measured by media analysis and presented through charts, tables and other graphical means: totals of media 'impressions', favourability ratings for companies and industries, leading issues, leading publications or TV/radio programmes, leading sources of information or opinion quoted in the media, successful and unsuccessful corporate messages, and leading 'bylines'. (author)

  14. Nuclear data evaluation method and evaluation system

    International Nuclear Information System (INIS)

    Liu Tingjin

    1995-01-01

    The evaluation methods and Nuclear Data Evaluation System have been developed in China. A new version of the system has been established on Micro-VAX2 computer, which is supported by IAEA under the technology assistance program. The flow chart of Chinese Nuclear Data Evaluation System is shown out. For last ten years, the main efforts have been put on the double differential cross section, covariance data and evaluated data library validation. The developed evaluation method and Chinese Nuclear Data Evaluation System have been widely used at CNDC and in Chinese Nuclear Data Network for CENDL. (1 tab., 15 figs.)

  15. Selecting of key safety parameters in reactor nuclear safety supervision

    International Nuclear Information System (INIS)

    He Fan; Yu Hong

    2014-01-01

    The safety parameters indicate the operational states and safety of research reactor are the basis of nuclear safety supervision institution to carry out effective supervision to nuclear facilities. In this paper, the selecting of key safety parameters presented by the research reactor operating unit to National Nuclear Safety Administration that can express the research reactor operational states and safety when operational occurrence or nuclear accident happens, and the interrelationship between them are discussed. Analysis shows that, the key parameters to nuclear safety supervision of research reactor including design limits, operational limits and conditions, safety system settings, safety limits, acceptable limits and emergency action level etc. (authors)

  16. Parameters Evaluation of PLC Dependability and Safety

    Directory of Open Access Journals (Sweden)

    Juraj Zdansky

    2006-01-01

    Full Text Available This paper is focused on evaluation of dependability and safety parameters of PLC (Programmable Logic Controller. Achievement of requested level of these parameters is an application assumption for using PLC in control of safety critical processes. Evaluation of these parameters can be made on the base of suitable model and it can be influenced by system architecture when necessary.

  17. International Nuclear Fuel Cycle Evaluation

    International Nuclear Information System (INIS)

    Carnesale, A.

    1980-01-01

    As nuclear power expands globally, so too expands the capability for producing nuclear weapons. The International Nuclear Fuel Cycle Evaluation (INFCE) was organized in 1977 for the purpose of exploring two areas: (1) ways in which nuclear energy can be made available to help meet world energy needs, and (2) means by which the attendant risk of weapons proliferation can be held to a minimum. INFCE is designed for technical and analytical study rather than negotiation. Its organizational structure and issues under consideration are discussed. Some even broader issues that emerge from consideration of the relationships between the peaceful and military use of nuclear energy are also discussed. These are different notions of the meaning of nuclear proliferation, nuclear export policy, the need of a nuclear policy to be both a domestic as well as a foreign one, and political-military measures that can help reduce incentives of countries to acquire nuclear weapons of their own

  18. Economic evaluation of nuclear plant project

    International Nuclear Information System (INIS)

    Tolba, Adel.

    1988-01-01

    The present work is an attempt to prepare a ''fair price'' estimate to serve as bench mark in the course of economic evaluation of bids to construct nuclear power plants. The methodology of determining the present value of all capital investment is used. Running costs of nuclear fuel, operation, and maintenance are also determined. As a result, levelized energy cost is calculated. Sensitivity analysis for different parameters has been conducted, and the results of which are included in this paper

  19. Using neural networks for prediction of nuclear parameters

    Energy Technology Data Exchange (ETDEWEB)

    Pereira Filho, Leonidas; Souto, Kelling Cabral, E-mail: leonidasmilenium@hotmail.com, E-mail: kcsouto@bol.com.br [Instituto Federal de Educacao, Ciencia e Tecnologia do Rio de Janeiro (IFRJ), Rio de Janeiro, RJ (Brazil); Machado, Marcelo Dornellas, E-mail: dornemd@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (GCN.T/ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). Gerencia de Combustivel Nuclear

    2013-07-01

    Dating from 1943, the earliest work on artificial neural networks (ANN), when Warren Mc Cullock and Walter Pitts developed a study on the behavior of the biological neuron, with the goal of creating a mathematical model. Some other work was done until after the 80 witnessed an explosion of interest in ANNs, mainly due to advances in technology, especially microelectronics. Because ANNs are able to solve many problems such as approximation, classification, categorization, prediction and others, they have numerous applications in various areas, including nuclear. Nodal method is adopted as a tool for analyzing core parameters such as boron concentration and pin power peaks for pressurized water reactors. However, this method is extremely slow when it is necessary to perform various core evaluations, for example core reloading optimization. To overcome this difficulty, in this paper a model of Multi-layer Perceptron (MLP) artificial neural network type backpropagation will be trained to predict these values. The main objective of this work is the development of Multi-layer Perceptron (MLP) artificial neural network capable to predict, in very short time, with good accuracy, two important parameters used in the core reloading problem - Boron Concentration and Power Peaking Factor. For the training of the neural networks are provided loading patterns and nuclear data used in cycle 19 of Angra 1 nuclear power plant. Three models of networks are constructed using the same input data and providing the following outputs: 1- Boron Concentration and Power Peaking Factor, 2 - Boron Concentration and 3 - Power Peaking Factor. (author)

  20. Using neural networks for prediction of nuclear parameters

    International Nuclear Information System (INIS)

    Pereira Filho, Leonidas; Souto, Kelling Cabral; Machado, Marcelo Dornellas

    2013-01-01

    Dating from 1943, the earliest work on artificial neural networks (ANN), when Warren Mc Cullock and Walter Pitts developed a study on the behavior of the biological neuron, with the goal of creating a mathematical model. Some other work was done until after the 80 witnessed an explosion of interest in ANNs, mainly due to advances in technology, especially microelectronics. Because ANNs are able to solve many problems such as approximation, classification, categorization, prediction and others, they have numerous applications in various areas, including nuclear. Nodal method is adopted as a tool for analyzing core parameters such as boron concentration and pin power peaks for pressurized water reactors. However, this method is extremely slow when it is necessary to perform various core evaluations, for example core reloading optimization. To overcome this difficulty, in this paper a model of Multi-layer Perceptron (MLP) artificial neural network type backpropagation will be trained to predict these values. The main objective of this work is the development of Multi-layer Perceptron (MLP) artificial neural network capable to predict, in very short time, with good accuracy, two important parameters used in the core reloading problem - Boron Concentration and Power Peaking Factor. For the training of the neural networks are provided loading patterns and nuclear data used in cycle 19 of Angra 1 nuclear power plant. Three models of networks are constructed using the same input data and providing the following outputs: 1- Boron Concentration and Power Peaking Factor, 2 - Boron Concentration and 3 - Power Peaking Factor. (author)

  1. Calculation of the well depth parameter to the nuclear potential

    International Nuclear Information System (INIS)

    Kim, Y.U.; Kim, Y.J.

    1984-01-01

    Well depth parameter S or range correction factor S-1 is computed for several nuclear potentials such as square, Gaussian, exponential and Yukawa wells. A simple central force is assumed for nuclear potential between nucleons. We adopted only two parameters for potentials and attempted to clarify the fundamental nature of the nuclear forces that bind a proton and a neutron into a deuteron. Results thus obtained were used for an estimate of first order correction to simple square well model. (Author)

  2. Correlation between nuclear perfusion parameters and duplex US indices in the diagnosis of renal allograft rejection

    International Nuclear Information System (INIS)

    Kim, E.E.; Maklad, N.F.; Pjura, G.A.; Lowry, P.A.

    1986-01-01

    Fifty nuclear perfusion and duplex US studies in 30 patients who had received renal allografts were prospectively analyzed to evaluate their respective measures of blood flow as indicators of rejection. The nuclear study (Tc-99m DTPA) generated three parameters, and a real-time, pulsed Doppler sector scanner generated resistance and pulsatility indices. In nine cases with a greater than 70% resistance index and 1.4 pulsatility index on US, the US findings correlated well with changes in nuclear perfusion parameters, indication rejection. The authors conclude that the combination of decreasing nuclear perfusion parameters and positive US indices may obviate the need for biopsy in the diagnosis of allograft rejection

  3. Evaluation of instrumental parameters for obtaining acceptable analytical results of the Dosimetry Laboratory of Chemistry of the Regional Center of Nuclear Sciences, CNEN-NE, Recife, Brazil

    International Nuclear Information System (INIS)

    Souza, V.L.B.; Figueiredo, M.D.C.; Cunha, M.S.

    2008-01-01

    Instrumental parameters need to be evaluated for obtaining acceptable analytical results for a specific instrument. The performance of the UV-VIS spectrophotometer can be verified for wavelengths and absorbances with appropriate materials (solutions of different concentrations of K 2 CrO 4 , for example). The aim of this work was to demonstrate the results of the procedures to control the quality of the measurements carried out in the laboratory in the last four years. The samples were analyzed in the spectrophotometer and control graphics were obtained for K 2 CrO 4 and Fe 3+ absorbance values. The variation in the results obtained for the stability of the spectrophotometer and for the control of its calibration did not exceed 2%. (author)

  4. Seismic evaluation of nuclear installations

    International Nuclear Information System (INIS)

    Mattar Neto, Miguel

    1997-01-01

    Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs

  5. Tables of nuclear level density parameters

    International Nuclear Information System (INIS)

    Chatterjee, A.; Ghosh, S.K.; Majumdar, H.

    1976-03-01

    The Renormalized Gas Model (RGM) has been used to calculate single particle level density parameters for more than 2000 nucleides over the range 9<=Z<=126 (15<=A<=338). Three separate tables present the elements on or near the valley of beta stability, neutron-rich fission fragment nucleides, and transitional nuclei, actinides and light-mass super heavy elements. Each table identifies the nucleus in terms of Z and N and presents the RGM deformation energy of binding, the total RGM structural energy correction over the free gas Fermi surface, and the level density parameter

  6. Nuclear Criticality Technology and Safety Project parameter study database

    International Nuclear Information System (INIS)

    Toffer, H.; Erickson, D.G.; Samuel, T.J.; Pearson, J.S.

    1993-03-01

    A computerized, knowledge-screened, comprehensive database of the nuclear criticality safety documentation has been assembled as part of the Nuclear Criticality Technology and Safety (NCTS) Project. The database is focused on nuclear criticality parameter studies. The database has been computerized using dBASE III Plus and can be used on a personal computer or a workstation. More than 1300 documents have been reviewed by nuclear criticality specialists over the last 5 years to produce over 800 database entries. Nuclear criticality specialists will be able to access the database and retrieve information about topical parameter studies, authors, and chronology. The database places the accumulated knowledge in the nuclear criticality area over the last 50 years at the fingertips of a criticality analyst

  7. Single-level resonance parameters fit nuclear cross-sections

    Science.gov (United States)

    Drawbaugh, D. W.; Gibson, G.; Miller, M.; Page, S. L.

    1970-01-01

    Least squares analyses of experimental differential cross-section data for the U-235 nucleus have yielded single level Breit-Wigner resonance parameters that fit, simultaneously, three nuclear cross sections of capture, fission, and total.

  8. Evaluation of safety-parameter display concepts. Final report

    International Nuclear Information System (INIS)

    Woods, D.D.; Wise, J.A.; Hanes, L.F.

    1982-02-01

    New control room equipment designed to improve operator performance must be evaluated before adoption and installation. Two experimental concepts for a Safety Parameters Display System (SPDS) were evaluated to assess benefits and potential problems associated with the SPDS concept and its integration into control room operations. Participants were licensed utility operators undergoing retraining on a nuclear power plant simulator. Both quantitative and qualitative data were collected and analyzed on crew response to seven simulated accident conditions

  9. Nuclear Matter Bulk Parameter Scales and Correlations

    International Nuclear Information System (INIS)

    Santos, B. M.; Delfino, A.; Dutra, M.; Lourenço, O.

    2015-01-01

    We study the arising of correlations among some isovector bulk parameters in nonrelativistic and relativistic hadronic mean-field models. For the former, we investigate correlations in the nonrelativistic (NR) limit of relativistic point-coupling models. We provide analytical correlations, for the NR limit model, between the symmetry energy and its derivatives, namely, the symmetry energy slope, curvature, skewness and fourth order derivative, discussing the conditions in which they are linear ones. We also show that some correlations presented in the NR limit model are reproduced for relativistic models presenting cubic and quartic self-interactions in its scalar field. As a direct application of such linear correlations, we remark its association with possible crossing points in the density dependence of the linearly correlated bulk parameter. (author)

  10. Landau parameters for finite range density dependent nuclear interactions

    International Nuclear Information System (INIS)

    Farine, M.

    1997-01-01

    The Landau parameters represent the effective particle-hole interaction at Fermi level. Since between the physical observables and the Landau parameters there is a direct relation their derivation from an effective interaction is of great interest. The parameter F 0 determines the incompressibility K of the system. The parameter F 1 determines the effective mass (which controls the level density at the Fermi level). In addition, F 0 ' determines the symmetry energy, G 0 the magnetic susceptibility, and G 0 ' the pion condensation threshold in nuclear matter. This paper is devoted to a general derivation of Landau parameters for an interaction with density dependent finite range terms. Particular carefulness is devoted to the inclusion of rearrangement terms. This report is part of a larger project which aims at defining a new nuclear interaction improving the well-known D1 force of Gogny et al. for describing the average nuclear properties and exotic nuclei and satisfying, in addition, the sum rules

  11. Nuclear models relevant to evaluation

    International Nuclear Information System (INIS)

    Arthur, E.D.; Chadwick, M.B.; Hale, G.M.; Young, P.G.

    1991-01-01

    The widespread use of nuclear models continues in the creation of data evaluations. The reasons include extension of data evaluations to higher energies, creation of data libraries for isotopic components of natural materials, and production of evaluations for radiative target species. In these cases, experimental data are often sparse or nonexistent. As this trend continues, the nuclear models employed in evaluation work move towards more microscopically-based theoretical methods, prompted in part by the availability of increasingly powerful computational resources. Advances in nuclear models applicable to evaluation will be reviewed. These include advances in optical model theory, microscopic and phenomenological state and level density theory, unified models that consistently describe both equilibrium and nonequilibrium reaction mechanism, and improved methodologies for calculation of prompt radiation from fission. 84 refs., 8 figs

  12. Parameters affecting level measurement interpretation of nuclear fuel solutions

    International Nuclear Information System (INIS)

    Hunt, B.A.; Landat, D.A.

    1999-01-01

    This paper describes a level measurement technique commonly used in the measurement of radioactive liquids and equipment utilised by the inspectors for safeguards purposes. Some of the influencing parameters affecting the measurement results by this technique are characterised. An essential requisite for successful process operations in chemical facilities involving liquids generally require some physical measurements to be made in-line for both process and quality control in order to achieve the necessary final product specifications . In nuclear fuel reprocessing facilities, the same objectives apply coupled however with an additional requirement of achieving nuclear material accountancy and control. In view of the strategic importance of some of the process vessels in nuclear facilities, accountancy has to be supported by volume and density measurements of low uncertainty. Inspectors therefore require instruments which are at the very least as good as or better than operator's equipment. The classical measurement technique and most widely applied for process liquids in nuclear installations is the bubbler probe or dip-tube technique. Here a regulated flow of air passes through tubes inserted to various depths into the vessel and pressure readings are measured which are a function of the presence of liquid height and density of solution in the tank. These readings, taken together with a pre-determined calibration curve are sufficient for the volume and amount of liquor in a tank to be quantified. All measurement equipment and instrumentation are long distances from the tank environment. The key physical parameter to measure at this location is therefore pressure. Equipment designed developed, commissioned and tested in the tank measurement facilities at Ispra and in nuclear installations in Europe, Japan and the USA, house digital pressure transducer modules with manufacture's declared features of better than 0.01% accuracy and long term stability of 0.01% full

  13. Selection and verification of safety parameters in safety parameter display system for nuclear power plants

    International Nuclear Information System (INIS)

    Zhang Yuangfang

    1992-02-01

    The method and results for safety parameter selection and its verification in safety parameter display system of nuclear power plants are introduced. According to safety analysis, the overall safety is divided into six critical safety functions, and a certain amount of safety parameters which can represent the integrity degree of each function and the causes of change are strictly selected. The verification of safety parameter selection is carried out from the view of applying the plant emergency procedures and in the accident man oeuvres on a full scale nuclear power plant simulator

  14. Study of nuclear level density parameter and its temperature dependence

    International Nuclear Information System (INIS)

    Nasrabadi, M. N.; Behkami, A. N.

    2000-01-01

    The nuclear level density ρ is the basic ingredient required for theoretical studies of nuclear reaction and structure. It describes the statistical nuclear properties and is expressed as a function of various constants of motion such as number of particles, excitation energy and angular momentum. In this work the energy and spin dependence of nuclear level density will be presented and discussed. In addition the level density parameter α will be extracted from this level density information, and its temperature and mass dependence will be obtained

  15. Evaluation of Haematological and Biochemical Parameters of ...

    African Journals Online (AJOL)

    ADOWIE PERE

    Evaluation of Haematological and Biochemical Parameters of Juvenile Oreochromis niloticus after Exposure to Water Soluble Fractions of ... niloticus were evaluated. After a preliminary determination of the 96 h-LC50 of ... evaporation, dissolution, emulsion, photolysis and biodegradation which generate a water soluble.

  16. Evaluation and processing of nuclear data

    International Nuclear Information System (INIS)

    Pearlstein, S.

    1981-01-01

    The role a nuclear data evaluator plays in obtaining evaluated nuclear data, needed for applications, from measured nuclear data is surveyed. Specific evaluation objectives, problems, and procedures are discussed. The use of nuclear systematics to complement nuclear experiment and theory is described. Using the Evaluated Nuclear Data File (ENDF) as an example the formatting, checking, and processing of nuclear data is discussed as well as the testing of evaluated nuclear data in the calculation of integral benchmark experiments. Other important topics such as the Probability Table Method and interrelation between differential and integral data are also discussed. (author)

  17. Evaluation and processing of nuclear data

    International Nuclear Information System (INIS)

    Pearlstein, S.

    1980-01-01

    The role a nuclear data evaluator plays in obtaining evaluated nuclear data, needed for applications, from measured nuclear data is surveyed. Specific evaluation objectives, problems, and procedures are discussed. The use of nuclear systematics to complement nuclear experiment and theory is described. With the Evaluated Nuclear Data File (ENDF) as an example, the formatting, checking, and processing of nuclear data are discussed as well as the testing of evaluated nuclear data in the calculation of integral benchmark experiments. Other important topics such as the Probability Table Method and interrelation between differential and integral data are also discussed. 25 figures

  18. Nuclear instrumentation evaluation and analysis

    International Nuclear Information System (INIS)

    Park, Suk Jun; Han, Sang Joon; Chung, Chong Eun; Han, Kwang Soo; Kim, Dong Hwa; Park, Byung Hae; Moon, Je Sun; Lee, Chel Kwon; Song, Ki Sang; Choi, Myung Jin; Kim, Seung Bok; Kim, Jung Bok

    1986-12-01

    This project provides the program for improving instrumentation reliability as well as developing a cost-effective preventive maintenance activity through evaluation and analysis of nuclear instrumentation concerning pilot plants, large-scale test facilities and various laboratories on KAERI site. In addition, it discusses the program for enhancing safe operations and improving facility availability through establishment of maintenance technology. (Author)

  19. Development of nuclear thermal hydraulic verification test and evaluation technology; study on 3-dimension measurement of two-phase flow parameters in subcooled boiling flow

    Energy Technology Data Exchange (ETDEWEB)

    Park, Goon Cherl; Kim, Moon Oh; Cho, Hyung Kyoo; Kim, Seong Jin [Seoul National University, Seoul (Korea)

    2002-04-01

    In this study, the experiments were conducted at different levels of inlet subcooling, flow rate and heat flux in a vertical concentric annulus channel located heater at the center with subcooled boiling conditions of atmosphere pressure and superficial velocity under 1.5m/s. The profiles of void fraction, vapor size, vapor frequency, vapor velocity and IAC were measured by 2 sensor conductivity probe in axially 3 points (L/D{sub h}=90.5,80.1,71.4) and those of liquid velocity by pitot tube. Based on the experiment data subcooled boiling models in MARS and multidimensional code, CFX-4.2 were evaluated was verified for analysis ability of these codes in subcooled boiling. 61 refs., 41 figs., 11 tabs. (Author)

  20. New evaluation parameter for wearable thermoelectric generators

    Science.gov (United States)

    Wijethunge, Dimuthu; Kim, Woochul

    2018-04-01

    Wearable devices constitute a key application area for thermoelectric devices. However, owing to new constraints in wearable applications, a few conventional device optimization techniques are not appropriate and material evaluation parameters, such as figure of merit (zT) and power factor (PF), tend to be inadequate. We illustrated the incompleteness of zT and PF by performing simulations and considering different thermoelectric materials. The results indicate a weak correlation between device performance and zT and PF. In this study, we propose a new evaluation parameter, zTwearable, which is better suited for wearable applications compared to conventional zT. Owing to size restrictions, gap filler based device optimization is extremely critical in wearable devices. With respect to the occasions in which gap fillers are used, expressions for power, effective thermal conductivity (keff), and optimum load electrical ratio (mopt) are derived. According to the new parameters, the thermal conductivity of the material has become much more critical now. The proposed new evaluation parameter, namely, zTwearable, is extremely useful in the selection of an appropriate thermoelectric material among various candidates prior to the commencement of the actual design process.

  1. Nuclear matter equation of state and σ-meson parameters

    Indian Academy of Sciences (India)

    We try to determine phenomenologically the extent of in-medium modification of -meson parameters so that the saturation observables of the nuclear matter equation of state (EOS) are reproduced. To calculate the EOS we have used Brueckner–Bethe–Goldstone formalism with Bonn potential as two-body interaction.

  2. Dependence of nuclear moments of inertia on the triaxial parameter

    International Nuclear Information System (INIS)

    Helgesson, J.; Hamamoto, Ikuko

    1989-01-01

    The dependence of nuclear moments of inertia on the triaxial parameter (γ-variable) is investigated including both the Belyaev term and the Migdal term. The obtained dependence is compared with that of hydrodynamical moments of inertia and other moments of inertia used conventionally. (orig.)

  3. Evaluation of safety parameter display concepts. Final report

    International Nuclear Information System (INIS)

    Woods, D.D.; Wise, J.A.; Hanes, L.F.

    1982-02-01

    New control room equipment designed to improve operator performance must be evaluated before adoption and installation. Two experimental concept for a Safety Parameters Display System (SPDS) were evaluated to assess benefits and potential problems associated with the SPDS concept and its integration into control room operations. Participants were licensed utility operators undergoing retraining on a nuclear power plant simulator. Both quantitative and qualitative data were collected and analyzed on crew response to seven simulated accident conditions. Data on operator decisions and actions have been organized into timelines. Analysis of the timelines and observations collected during testing provide important insights about the potential impact of the SPDS concept on control room operations

  4. IAEA nuclear data for applications: Cross section standards and the reference input parameter library (RIPL)

    International Nuclear Information System (INIS)

    Capote Noy, Roberto; Nichols, Alan L.; Pronyaev, Vladimir G.

    2003-01-01

    An integral part of the activities of the IAEA Nuclear Data Section involves the development of nuclear data for a wide range of user applications. When considering low-energy nuclear reactions induced by neutrons, photons and charged particles, a detailed knowledge is required of the production cross sections over a wide energy range, spectra of emitted particles and their angular distributions. Two highly relevant IAEA data development projects are considered in this paper. Neutron reaction cross-section standards represent the basic quantities needed in nuclear reaction cross-section measurements and evaluations. These standards and the covariance matrices of their uncertainties were previously evaluated and released in 1987. However, the derived uncertainties were subsequently considered to be unrealistic low due to the effect of the low uncertainties obtained in fitting the light element standards to the R-matrix model; as a result, evaluators were forced to scale up the uncertainties to 'expected values'. An IAEA Coordinated Research Project (CRP) entitled 'Improvement of the Standard Cross Sections for Light Elements' was initiated in 2002 to improve the evaluation methodology for the covariance matrix of uncertainty in the R-matrix model fits, and to produce R-matrix evaluations of the important light element standards. The scope of this CRP has been substantially extended to include the preparation of a full set of evaluated standard reactions and covariance matrices of their uncertainties. While almost all requests for nuclear data were originally addressed through measurement programmes, our theoretical understanding of nuclear phenomena has reached a reasonable degree of reliability and nuclear modeling has become standard practice in nuclear data evaluations (with measurements remaining crucial for data testing and benchmarking). Since nuclear model codes require a considerable amount of numerical input, the IAEA has instigated extensive efforts to

  5. Nuclear explosives testing readiness evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Valk, T.C.

    1993-09-01

    This readiness evaluation considers hole selection and characterization, verification, containment issues, nuclear explosive safety studies, test authorities, event operations planning, canister-rack preparation, site preparation, diagnostic equipment setup, device assembly facilities and processes, device delivery and insertion, emplacement, stemming, control room activities, readiness briefing, arming and firing, test execution, emergency response and reentry, and post event analysis to include device diagnostics, nuclear chemistry, and containment. This survey concludes that the LLNL program and its supporting contractors could execute an event within six months of notification, and a second event within the following six months, given the NET group`s evaluation and the following three restraints: (1) FY94 (and subsequent year) funding is essentially constant with FY93, (2) Preliminary work for the initial event is completed to the historical sic months status, (3) Critical personnel, currently working in dual use technologies, would be recallable as needed.

  6. Correction factors for photon spectrometry in nuclear parameters study

    International Nuclear Information System (INIS)

    Patrao, Karla Cristina de Souza

    2004-10-01

    The goal of this work was the determination, using metrologic severity, the factors of correction for coincidences XX, Xγ and γγ and the factors of transference of efficiency for use in gamma spectrometry. On this way, it was carried through by determination of nuclear parameters of a nuclide used in medicine diagnostic ( 201 Tl) and the standardization of two environmental samples, of regular and irregular geometry, proceeding from the residual (ashes and slag) from the nuclear industry. The results shows that this adopted methodology is valid, and it allows its application for many different nuclides, including complex decay schema nuclides, using only photons spectrometry techniques on semiconductor detectors. (author)

  7. Nuclear data, their importance and evaluation

    International Nuclear Information System (INIS)

    Schmidt, J.J.

    1980-01-01

    Nuclear data comprize all quantitative results of nuclear physics investigations and can be subdivided in the three areas of nuclear structure, nuclear decay and nuclear reaction data. For the purposes of fission and fusion reactor design mostly neutron reaction data are needed, while for the nuclear fuel cycle outside the reactor and for a large variety of ''non-energy'' scientific applications a number of photonuclear and charged particle nuclear reaction data and of nuclear structure and decay data are needed, in addition to selected neutron nuclear reaction data. To meet the needs of nuclear science and technology for accurate nuclear data, comprehensive computer libraries of evaluated nuclear data have been built up from evaluation of a massive volume of experimental data complemented by data calculated from nuclear theory. The basic characteristics and requirements of evaluated data libraries are discussed and evaluation sources and methods illustrated with the example of a few important neutron nuclear reactions. International mechanisms have been developed, coordinated by the IAEA Nuclear Data Section with the cooperation of many nuclear data centres and groups, for the efficient dissemination of bibliographic and numerical experimental and evaluated nuclear data to data users in the whole world. (author)

  8. Parameter identification in a nonlinear nuclear reactor model using quasilinearization

    International Nuclear Information System (INIS)

    Barreto, J.M.; Martins Neto, A.F.; Tanomaru, N.

    1980-09-01

    Parameter identification in a nonlinear, lumped parameter, nuclear reactor model is carried out using discrete output power measurements during the transient caused by an external reactivity change. In order to minimize the difference between the model and the reactor power responses, the parameter promt neutron generation time and a parameter in fuel temperature reactivity coefficient equation are adjusted using quasilinearization. The influences of the external reactivity disturbance, the number and frequency of measurements and the measurement noise level on the method accuracy and rate of convergence are analysed through simulation. Procedures for the design of the identification experiments are suggested. The method proved to be very effective for low level noise measurements. (Author) [pt

  9. Angular momentum dependence of the nuclear level density parameter

    International Nuclear Information System (INIS)

    Aggarwal, Mamta; Kailas, S.

    2010-01-01

    Dependence of nuclear level density parameter on the angular momentum and temperature is investigated in a theoretical framework using the statistical theory of hot rotating nuclei. The structural effects are incorporated by including shell correction, shape, and deformation. The nuclei around Z≅50 with an excitation energy range of 30 to 40 MeV are considered. The calculations are in good agreement with the experimentally deduced inverse level density parameter values especially for 109 In, 113 Sb, 122 Te, 123 I, and 127 Cs nuclei.

  10. Microscopic analysis of order parameters in nuclear quantum phase transitions

    International Nuclear Information System (INIS)

    Li, Z. P.; Niksic, T.; Vretenar, D.; Meng, J.

    2009-01-01

    Microscopic signatures of nuclear ground-state shape phase transitions in Nd isotopes are studied using excitation spectra and collective wave functions obtained by diagonalization of a five-dimensional Hamiltonian for quadrupole vibrational and rotational degrees of freedom, with parameters determined by constrained self-consistent relativistic mean-field calculations for triaxial shapes. As a function of the physical control parameter, the number of nucleons, energy gaps between the ground state and the excited vibrational states with zero angular momentum, isomer shifts, and monopole transition strengths exhibit sharp discontinuities at neutron number N=90, which is characteristic of a first-order quantum phase transition.

  11. Nuclear level density parameter 's dependence on angular momentum

    International Nuclear Information System (INIS)

    Aggarwal, Mamta; Kailas, S.

    2009-01-01

    Nuclear level densities represent a very important ingredient in the statistical Model calculations of nuclear reaction cross sections and help to understand the microscopic features of the excited nuclei. Most of the earlier experimental nuclear level density measurements are confined to low excitation energy and low spin region. A recent experimental investigation of nuclear level densities in high excitation energy and angular momentum domain with some interesting results on inverse level density parameter's dependence on angular momentum in the region around Z=50 has motivated us to study and analyse these experimental results in a microscopic theoretical framework. In the experiment, heavy ion fusion reactions are used to populate the excited and rotating nuclei and measured the α particle evaporation spectra in coincidence with ray multiplicity. Residual nuclei are in the range of Z R 48-55 with excitation energy range 30 to 40 MeV and angular momentum in 10 to 25. The inverse level density parameter K is found to be in the range of 9.0 - 10.5 with some exceptions

  12. Diagnostics and tolerance optimization of nuclear facilities parameters

    International Nuclear Information System (INIS)

    Novak, M.; Otcenasek, P.

    1988-01-01

    The possibilities are discussed of applying the theory of tolerances for assessing the service life of systems in nuclear power. The approach proceeds from the postulate that the nuclear power plant is on the one hand an extremely sophisticated technical system and on the other a system with well defined demands on the state and properties of components and of the whole system, with rationally defined limits, conditions of permissible states and limit values. It is stated that the basic ideas of the theory of the hot channel may be extended and generalized. The theory was initially limited to the study of relations between deviations in nucleaer and non-nuclear parameters in the fuel assembly, and the temperature field; it can be generalized to the analysis of permissible parameter tolerances of the whole system. The foundations are outlined of the theory of tolerances of general technical system parameters. Brief attention is also paid to the general possibilities of the use of life curves for designing the system such as would extend its service life. (Z.M.). 10 figs., 5 refs

  13. Relationship between basic nuclear data and LWR fuel cycle parameters

    International Nuclear Information System (INIS)

    Becker, M.; Harris, D.R.; Quan, B.; Ryskamp, J.M.

    1979-01-01

    An interactive system has been developed at RPI to analyze the sensitivity of water reactor fuel cycle parameters and costs to uncertainties in nuclear data. A sequence of batch depletion, core analysis, and fuel cost codes (referred to as Path B) determines the changes in fuel cycle parameters and costs for changes in few-group microscopic cross sections, in fission yields, and in decay data. For cases that are found to be significant from Part B analysis, the sensitivities of few-group data to basic nuclear data are determined by detailed calculations (referred to as Path A). Analyses of pressurized and boiling water reactors with recycle and throwaway options show substantial sensitivities of fuel cycle parameters and costs, particularly to thermal and resonance nuclear data for fissile nuclides. The results bring out the importance for power reactor sensitivity analysis of dealing with the full fuel cycle including depletion of initially-loaded fuel and the building-in of actinides and fission products

  14. Nuclear Fuel Cycle Evaluation and Real Options

    Directory of Open Access Journals (Sweden)

    L. Havlíček

    2008-01-01

    Full Text Available The first part of this paper describes the nuclear fuel cycle. It is divided into three parts. The first part, called Front-End, covers all activities connected with fuel procurement and fabrication. The middle part of the cycle includes fuel reload design activities and the operation of the fuel in the reactor. Back-End comprises all activities ensuring safe separation of spent fuel and radioactive waste from the environment. The individual stages of the fuel cycle are strongly interrelated. Overall economic optimization is very difficult. Generally, NPV is used for an economic evaluation in the nuclear fuel cycle. However the high volatility of uranium prices in the Front-End, and the large uncertainty of both economic and technical parameters in the Back-End, make the use of NPV difficult. The real option method is able to evaluate the value added by flexibility of decision making by a company under conditions of uncertainty. The possibility of applying this method to the nuclear fuel cycle evaluation is studied. 

  15. Differential diagnosis of well-differentiated squamous cell carcinoma from non-neoplastic oral mucosal lesions: New cytopathologic evaluation method dependent on keratinization-related parameters but not nuclear atypism.

    Science.gov (United States)

    Hara, Hitoshi; Misawa, Tsuneo; Ishii, Eri; Nakagawa, Miki; Koshiishi, Saki; Amemiya, Kenji; Oyama, Toshio; Tominaga, Kazuya; Cheng, Jun; Tanaka, Akio; Saku, Takashi

    2017-05-01

    The cytology of oral squamous cell carcinoma (SCC) is challenging because oral SCC cells tend to be well differentiated and lack nuclear atypia, often resulting in a false negative diagnosis. The purpose of this study was to establish practical cytological parameters specific to oral SCCs. We reviewed 123 cases of malignancy and 53 of non-neoplastic lesions of the oral mucosa, which had been diagnosed using both cytology and histopathology specimens. From those, we selected 12 SCC and 4 CIS cases that had initially been categorized as NILM to ASC-H with the Bethesda system, as well as 4 non-neoplastic samples categorized as LSIL or ASC-H as controls, and compared their characteristic findings. After careful examinations, we highlighted five cytological parameters, as described in Results. Those 20 cytology samples were then reevaluated by 4 independent examiners using the Bethesda system as well as the 5 parameters. Five cytological features, (i) concentric arrangement of orangeophilic cells (indicating keratin pearls), (ii) large number of orangeophilic cells, (iii) bizarre-shaped orangeophilic cells without nuclear atypia, (iv) keratoglobules, and (v) uneven filamentous cytoplasm, were found to be significant parameters. All malignant cases contained at least one of those parameters, while none were observed in the four non-neoplastic cases with nuclear atypia. In reevaluations, the Bethesda system did not help the screeners distinguish oral SCCs from non-neoplastic lesions, while use of the five parameters enabled them to make a diagnosis of SCC. Recognition of the present five parameters is useful for oral SCC cytology. Diagn. Cytopathol. 2017;45:406-417. © 2017 Wiley Periodicals, Inc. © 2017 Wiley Periodicals, Inc.

  16. Nuclear data adjustment methodology utilizing resonance parameter sensitivities and uncertainties

    International Nuclear Information System (INIS)

    Broadhead, B.L.

    1983-01-01

    This work presents the development and demonstration of a Nuclear Data Adjustment Method that allows inclusion of both energy and spatial self-shielding into the adjustment procedure. The resulting adjustments are for the basic parameters (i.e. resonance parameters) in the resonance regions and for the group cross sections elsewhere. The majority of this development effort concerns the production of resonance parameter sensitivity information which allows the linkage between the responses of interest and the basic parameters. The resonance parameter sensitivity methodology developed herein usually provides accurate results when compared to direct recalculations using existng and well-known cross section processing codes. However, it has been shown in several cases that self-shielded cross sections can be very non-linear functions of the basic parameters. For this reason caution must be used in any study which assumes that a linear relatonship exists between a given self-shielded group cross section and its corresponding basic data parameters. The study also has pointed out the need for more approximate techniques which will allow the required sensitivity information to be obtained in a more cost effective manner

  17. International nuclear fuel cycle evaluation

    International Nuclear Information System (INIS)

    Witt, P.

    1980-01-01

    In the end of February 1980, the two-years work on the International Nuclear Fuel Cycle Evaluation (INFCE) was finished in Vienna with a plenary meeting. INFCE is likely to have been a unique event in the history of international meetings: It was ni diplomatic negotiation meeting, but a techno-analytical investigation in which the participants tenaciously shuggled for many of the formulations. Starting point had been a meeting initiated by President Carter in Washington in Oct. 1979 after the World Economy Summit Meeting in London. The results of the investigation are presented here in a brief and popular form. (orig./UA) [de

  18. Neutron nuclear data evaluation for actinide nucleic

    International Nuclear Information System (INIS)

    Chen Guochang; Yu Baosheng; Duan Junfeng; Ge Zhigang; Cao Wentian; Tang Guoyou; Shi Zhaomin; Zou Yubin

    2010-01-01

    The nuclear data with high accuracy for minor actinides are playing an important role in nuclear technology applications, including reactor design and operation, fuel cycle concepts, estimation of the amount of minor actinides in high burn-up reactors and the minor actinides transmutation. Through describe the class of nuclear data and nuclear date library, and introduce the procedure of neutron nuclear data evaluation. 234 U(n, f) and 237 Np(n, 2n) reaction experimental data evaluation was evaluated. The fission nuclear data are updated and improved. (authors)

  19. Three-dimensional Monte Carlo calculation of some nuclear parameters

    Science.gov (United States)

    Günay, Mehtap; Şeker, Gökmen

    2017-09-01

    In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel structural material and the molten salt-heavy metal mixtures 99-95% Li20Sn80 + 1-5% RG-Pu, 99-95% Li20Sn80 + 1-5% RG-PuF4, and 99-95% Li20Sn80 + 1-5% RG-PuO2, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion-fission hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplication between the liquid first wall and blanket. This study analyzes the nuclear parameters such as tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate, fission reaction rate in liquid first wall, blanket and shield zones and investigates effects of reactor grade Pu content in the designed system on these nuclear parameters. Three-dimensional analyses were performed by using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.

  20. Three-dimensional Monte Carlo calculation of some nuclear parameters

    Directory of Open Access Journals (Sweden)

    Günay Mehtap

    2017-01-01

    Full Text Available In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel structural material and the molten salt-heavy metal mixtures 99–95% Li20Sn80 + 1-5% RG-Pu, 99–95% Li20Sn80 + 1-5% RG-PuF4, and 99–95% Li20Sn80 + 1-5% RG-PuO2, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion–fission hybrid reactor system. Beryllium (Be zone with the width of 3 cm was used for the neutron multiplication between the liquid first wall and blanket. This study analyzes the nuclear parameters such as tritium breeding ratio (TBR, energy multiplication factor (M, heat deposition rate, fission reaction rate in liquid first wall, blanket and shield zones and investigates effects of reactor grade Pu content in the designed system on these nuclear parameters. Three-dimensional analyses were performed by using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.

  1. Seismic evaluation of existing nuclear facilities. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    Programmes for re-evaluation and upgrading of safety of existing nuclear facilities are presently under way in a number of countries around the world. An important component of these programmes is the re-evaluation of the seismic safety through definition of new seismic parameters at the site and evaluation of seismic capacity of structures, equipment and distribution systems following updated information and criteria. The Seminar is intended to provide a forum for the exchange of information and discussion of the state-of-the-art on seismic safety of nuclear facilities in operation or under construction. Both analytical and experimental techniques for the evaluation of seismic capacity of structures, equipment and distribution systems are discussed. Full scale and field tests of structures and components using shaking tables, mechanical exciters, explosive and shock tests, and ambient vibrations are included in the seminar programme with emphasis on recent case histories. Presentations at the Seminar also include analytical techniques for the determination of dynamic properties of soil-structure systems from experiments as well as calibration of numerical models. Methods and criteria for seismic margin assessment based on experience data obtained from the behaviour of structures and components in real earthquakes are discussed. Guidelines for defining technical requirements for capacity re-evaluation (i.e. acceptable behaviour limits and design and implementation of structure and components upgrades are also presented and discussed. The following topics were covered during 7 sessions: earthquake experience and seismic re-evaluation; country experience in seismic re-evaluation programme; generic WWER studies; analytical methods for seismic capacity re-evaluation; experimental methods for seismic capacity re-evaluation; case studies.

  2. Seismic evaluation of existing nuclear facilities. Proceedings

    International Nuclear Information System (INIS)

    1995-01-01

    Programmes for re-evaluation and upgrading of safety of existing nuclear facilities are presently under way in a number of countries around the world. An important component of these programmes is the re-evaluation of the seismic safety through definition of new seismic parameters at the site and evaluation of seismic capacity of structures, equipment and distribution systems following updated information and criteria. The Seminar is intended to provide a forum for the exchange of information and discussion of the state-of-the-art on seismic safety of nuclear facilities in operation or under construction. Both analytical and experimental techniques for the evaluation of seismic capacity of structures, equipment and distribution systems are discussed. Full scale and field tests of structures and components using shaking tables, mechanical exciters, explosive and shock tests, and ambient vibrations are included in the seminar programme with emphasis on recent case histories. Presentations at the Seminar also include analytical techniques for the determination of dynamic properties of soil-structure systems from experiments as well as calibration of numerical models. Methods and criteria for seismic margin assessment based on experience data obtained from the behaviour of structures and components in real earthquakes are discussed. Guidelines for defining technical requirements for capacity re-evaluation (i.e. acceptable behaviour limits and design and implementation of structure and components upgrades are also presented and discussed. The following topics were covered during 7 sessions: earthquake experience and seismic re-evaluation; country experience in seismic re-evaluation programme; generic WWER studies; analytical methods for seismic capacity re-evaluation; experimental methods for seismic capacity re-evaluation; case studies

  3. Nuclear EMP: key suppression device parameters for EMP hardening

    International Nuclear Information System (INIS)

    Durgin, D.L.; Brown, R.M.

    1975-03-01

    The electrical transients induced by EMP exhibit unique characteristics which differ considerably from transients associated with other phenomena such as lightning, switching, and circuit malfunctions. The suppression techniques developed to handle more common transients, though not necessarily the same devices, can be used for EMP damage protection. The suppression devices used for circuit level EMP protection are referred to as Terminal Protection Devices (TPD). Little detailed data describing the response of TPD's to EMP-related transients have been published. While most vendors publish specifications for TPD performance, there is little standardization of parameters and TPD response models are not available. This lack of parameter standardization has resulted in a proliferation of test data that is sometimes conflicting and often not directly comparable. This paper derives and/or defines a consistent set of parameters based on EMP circuit hardening requirements and on measurable component parameters and is concerned only with use of TPD's to prevent permanent damage. Three sets of parameters pertaining to pertinent TPD functional characteristics were defined as follows: standby parameters, protection parameters, and failure parameters. These parameters are used to evaluate a representative sample of TPD's and the results are presented in matrix form to facilitate the selection of devices for specific hardening problems

  4. Computation of nuclear reactor parameters using a stretch Kalman filtering

    International Nuclear Information System (INIS)

    Zwingelstein, G.; Poujol, A.

    1976-01-01

    A method of nonlinear stochastic filtering, the stretched Karman filter, is used for the estimation of two basic parameters involved in the control of nuclear reactor start-up. The corresponding algorithm is stored in a small Multi-8 computer and tested with data recorded for the Ulysse reactor (I.N.S.T.N.). The various practical problems involved in using the algorithm are examined: filtering initialization, influence of the model... The quality and time saving obtained in the computation make it possible for a real time operation, the computer being connected with the reactor [fr

  5. The design of virtual double-parameter nuclear spectrum acquisition system based on LabVIEW

    International Nuclear Information System (INIS)

    Liu Songqiu; Chen Chuan; Lei Wuhu

    2001-01-01

    This paper introduces the design of virtual double-parameter nuclear spectrum acquisition system based on LabVIEW and NI multifunction DAQ board, and the use of it to measure the double-parameter nuclear spectrum

  6. Establishment of nuclear data evaluation system (I)

    International Nuclear Information System (INIS)

    Chang, Jong Hwa; Lee, Chang Kun; Kim, Jeong Do; Kim, Young Sik; Kim, Young Jin; Kim, Hyung Guk; Kil, Chung Sup; Kim, Kang Suk

    1994-08-01

    Nuclear data is fundamental data for development of new type of nuclear, upgrade of nuclear fuel, treatment of radwaste, research on fusion reactor, radioisotope usage, and nuclear medical therapy. Nuclear data is produced with experiments. However rack of experimental data for thousands of nuclides and various reaction types makes it essential to do statistical evaluation and theoretical interpolation. This study is intended to join international cooperation after establishing domestic basis for nuclear data evaluation work. This project is the first year of five year plan to do followings: 1) Establishment of database system to collect experimental data, 2) Setup of computer assistance system for evaluation work, 3) Verification of established system by test evaluation of selected nuclide reaction. The system has a collection of mass data of nuclides, computer codes for test evaluation of total cross section of 0-16 and collection of EXFOR format data for 0-16. This system will be improved continuously on next years. (Author)

  7. Seismic evaluation of nuclear installations; Avaliacao sismica de instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Mattar Neto, Miguel [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1997-10-01

    Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs.

  8. Status of Nuclear Safety evaluation in China

    International Nuclear Information System (INIS)

    Tian Jiashu

    1999-01-01

    Chinese nuclear safety management and control follows international practice, the regulations are mainly from IAEA with the Chinese condition. The regulatory body is National Nuclear Safety Administration (NNSA). The nuclear safety management, surveillance, safety review and evaluation are guided by NNSA with technical support by several units. Beijing Review Center of Nuclear Safety is one of these units, which was founded in 1987 within Beijing Institute of nuclear Engineering (BINE), co-directed by NNSA and BINE, it is the first technical support team to NNSA. Most of the safety reviews and evaluations of Chinese nuclear installations has been finished by this unit. It is described briefly in this paper that the NNSA's main function and organization, regulations on the nuclear safety, procedure of application and issuing of license, the main activities performed by Beijing Review Center of Nuclear Safety, the situation of severe accident analyses in China, etc. (author)

  9. Evaluation of Mechanical Parameters of Pellets

    Directory of Open Access Journals (Sweden)

    Ľubomír Kubík

    2016-01-01

    Full Text Available The paper dealt with the evaluation of mechanical properties of the cylinder wheat straw, rapeseed straw and 50/50 % mixed wheat and rapeseed straw pellet samples. The pellets were made by the granulating machine MGL 200 (Kovonovak. The compressive loading curves of dependencies of stress on strain were realised by the test stand Andilog Stentor 1000 (Andilog Technologies, Vitrolles, France. Certain mechanical parameters were determined, namely the initial force (force at 10 % of compress strain, force in maximum of loading curve, strain in maximum of loading curve, initial stress (stress at 10 % of compression strain, stress in maximum of loading curve and modulus of elasticity. Mean value of the initial force was maximal for mixed straw pellet samples 52.49 N. Mean values of the initial force of the wheat straw samples and the rapeseed straw samples were smaller and almost identical 43.58 N and 43.12 N. Mean values of the initial stress of loading curve, of the wheat straw samples reached 1.46 MPa, the rapeseed straw samples reached value 1.40 MPa and the mixed straw samples reached value 1.63 MPa. Mean value of the force in maximum of loading curve was also maximal for mixed straw pellet samples 213.26 N. Mean values of the force in maximum of loading curve of the wheat straw samples reached 178.11 N. The rapeseed straw samples reached value 95.95 N and the mixed straw samples reached value 213.26 N. Mean values of the stress in maximum of loading curve, of the wheat straw samples reached 5.93 MPa, the rapeseed straw samples reached value 3.11 MPa and the mixed straw samples reached value 7.10 MPa Mean values of the modulus of elasticity, of the wheat straw samples reached 18.27 MPa, the rapeseed straw samples reached value 13.08 MPa and the mixed straw samples reached value 14.97 MPa. Significant correlations of the mechanical parameters pellet samples were observed among initial force and initial stress and modulus of elasticity

  10. Pion parameters in nuclear medium from chiral perturbation theory and virial expansion

    International Nuclear Information System (INIS)

    Mallik, S.; Sarkar, Sourav

    2004-01-01

    We consider two methods to find the effective parameters of the pion traversing a nuclear medium. One is the first order chiral perturbation theoretic evaluation of the pion pole contribution to the two-point function of the axial-vector current. The other is the exact, first order virial expansion of the pion self-energy. We find that, although the results of chiral perturbation theory are not valid at normal nuclear density, those from the virial expansion may be reliable at such density. The latter predicts both the mass shift and the in-medium decay width of the pion to be small, of about a few MeV

  11. Dynamic testing of nuclear power plant structures: an evaluation

    International Nuclear Information System (INIS)

    Weaver, H.J.

    1980-02-01

    Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes work in three main areas: (1) analytical qualification of a set of computer programs developed at LLL to extract model parameters from the time histories; (2) examination of the feasibility of safely exciting nuclear power plant structures and accurately recording the resulting time-history motions; (3) study of how the model parameters that are extracted from the data be used best to evaluate structural integrity and analyze nuclear power plants

  12. TRITOX: a multiple parameter evaluation of tritium toxicity

    International Nuclear Information System (INIS)

    Carsten, A.L.

    1982-01-01

    The increased use of nuclear reactors for power generation will lead to the introduction of tritium into the environment. The need for assessing possible immediate and long-term effects of exposure to this tritium led to the development of a broad program directed towards evaluating the possible somatic and genetic effects of continuous exposure to tritiated water (HTO). Among the parameters measured are the genetic, cytogenetic, reproductive efficiency, growth, nonspecific lifetime shortening, bone marrow cellularity and stem cell content, relative biological effectiveness as compared to 137 Cesium gamma exposure, and related biochemical and microdosimetric evaluations. These parameters have been evaluated on animals maintained on HTO at 10 to 100 times the maximum permissible concentration (0.03 - 3.0 μCi/ml) for HTO. Dominant lethal mutations, chromosome aberrations in regenerating liver, increased sister chromatid exchanges in bone marrow and reduction in bone marrow stem cell content have been observed at the higher concentrations. The relative biological effectiveness for HTO ingestion as compared to external 137 Cesium gamma exposures has been found to be between 1 and 2

  13. Evaluation and analysis of nuclear resonance data

    International Nuclear Information System (INIS)

    Frohner, F.H.

    2000-01-01

    A probabilistic foundations of data evaluation are reviewed, with special emphasis on parameter estimation based on Bayes' theorem and a quadratic loss function, and on modern methods for the assignment of prior probabilities. The data reduction process leading from raw experimental data to evaluated computer files of nuclear reaction cross sections is outlined, with a discussion of systematic and statistical errors and their propagation and of the generalized least squares formalism including prior information and nonlinear theoretical models. It is explained how common errors induce correlations between data, what consequences they have for uncertainty propagation and sensitivity studies, and how evaluators can construct covariance matrices from the usual error information provided by experimentalists. New techniques for evaluation of inconsistent data are also presented. The general principles are then applied specifically to the analysis and evaluation of neutron resonance data in terms of theoretical models - R-matrix theory (and especially its practically used multi-level Breit-Wigner and Reich-Moore variants) in the resolved region, and resonance-averaged R-matrix theory (Hauser-Feshbach theory with width-fluctuation corrections) in the unresolved region. Complications arise because the measured transmission data, capture and fission yields, self-indication ratios and other observables are not yet the wanted cross sections. These are obtained only by means of parametrisation. The intervening effects - Doppler and resolution broadening, self-shielding, multiple scattering, backgrounds, sample impurities, energy-dependent detector efficiencies, inaccurate reference data etc - are therefore also discussed. (author)

  14. DOZIM - evaluation dose code for nuclear accident

    International Nuclear Information System (INIS)

    Oprea, I.; Musat, D.; Ionita, I.

    2008-01-01

    During a nuclear accident an environmentally significant fission products release can happen. In that case it is not possible to determine precisely the air fission products concentration and, consequently, the estimated doses will be affected by certain errors. The stringent requirement to cope with a nuclear accident, even minor, imposes creation of a computation method for emergency dosimetric evaluations needed to compare the measurement data to certain reference levels, previously established. These comparisons will allow a qualified option regarding the necessary actions to diminish the accident effects. DOZIM code estimates the soil contamination and the irradiation doses produced either by radioactive plume or by soil contamination. Irradiations either on whole body or on certain organs, as well as internal contamination doses produced by isotope inhalation during radioactive plume crossing are taken into account. The calculus does not consider neither the internal contamination produced by contaminated food consumption, or that produced by radioactive deposits resuspension. The code is recommended for dose computation on the wind direction, at distances from 10 2 to 2 x 10 4 m. The DOZIM code was utilized for three different cases: - In air TRIGA-SSR fuel bundle destruction with different input data for fission products fractions released into the environment; - Chernobyl-like accident doses estimation; - Intervention areas determination for a hypothetical severe accident at Cernavoda Nuclear Power Plant. For the first case input data and results (for a 60 m emission height without iodine retention on active coal filters) are presented. To summarize, the DOZIM code conception allows the dose estimation for any nuclear accident. Fission products inventory, released fractions, emission conditions, atmospherical and geographical parameters are the input data. Dosimetric factors are included in the program. The program is in FORTRAN IV language and was run on

  15. Nuclear theory for fast neutron nuclear data evaluation

    International Nuclear Information System (INIS)

    1988-11-01

    The proceedings contain all invited and contributed papers presented at the Advisory Group Meeting on Nuclear Theory for Fast Neutron Data Evaluation held in Beijing 12-16 October 1987, as well as the conclusions and recommendations and the Chairman's summary of the meeting. The meeting presentations have been divided into six sessions devoted to the following topics: introductory speech (1 paper), optical potential (9 papers), compound nuclear theory (10 papers), pre-compound nuclear theory (13 papers), isomeric cross-section (1 paper) and intercomparison of nuclear model computer codes (1 paper). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  16. SIMCRI: a simple computer code for calculating nuclear criticality parameters

    International Nuclear Information System (INIS)

    Nakamaru, Shou-ichi; Sugawara, Nobuhiko; Naito, Yoshitaka; Katakura, Jun-ichi; Okuno, Hiroshi.

    1986-03-01

    This is a user's manual for a simple criticality calculation code SIMCRI. The code has been developed to facilitate criticality calculation on a single unit of nuclear fuel. SIMCRI makes an extensive survey with a little computing time. Cross section library MGCL for SIMCRI is the same one for the Monte Carlo criticality code KENOIV; it is, therefore, easy to compare the results of the two codes. SIMCRI solves eigenvalue problems and fixed source problems based on the one space point B 1 equation. The results include infinite and effective multiplication factor, critical buckling, migration area, diffusion coefficient and so on. SIMCRI is comprised in the criticality safety evaluation code system JACS. (author)

  17. Economic evaluation of multilateral nuclear fuel cycle approach

    International Nuclear Information System (INIS)

    Takashima, Ryuta; Kuno, Yusuke; Omoto, Akira; Tanaka, Satoru

    2011-01-01

    Recently previous works have shown that multilateral nuclear fuel cycle approach has benefits not only of non-proliferation but also of cost effectiveness. This is because for most facilities in nuclear fuel cycle, there exist economies of scale, which has a significant impact on the costs of nuclear fuel cycle. Therefore, the evaluation of economic rationality is required as one of the evaluation factors for the multilateral nuclear fuel cycle approach. In this study, we consider some options with respect to multilateral approaches to nuclear fuel cycle in Asian-Pacific region countries that are proposed by the University of Tokyo. In particular, the following factors are embedded into each type: A) no involvement of assurance of services, B) provision of assurance of services including construction of new facility, without transfer of ownership, and C) provision of assurance of service including construction of new joint facilities with ownership transfer of facilities to multilateral nuclear fuel cycle approach. We show the overnight costs taking into account install and operation of nuclear fuel cycle facilities for each option. The economic parameter values such as uranium price, scale factor, and market output expansion influences the total cost for each option. Thus, we show how these parameter values and economic risks affect the total overnight costs for each option. Additionally, the international facilities could increase the risk of transportation for nuclear material compared to national facilities. We discuss the potential effects of this transportation risk on the costs for each option. (author)

  18. Tracking of nuclear reactor parameters via recursive non linear estimation

    International Nuclear Information System (INIS)

    Pages Fita, J.; Alengrin, G.; Aguilar Martin, J.; Zwingelstein, M.

    1975-01-01

    The usefulness of nonlinear estimation in the supervision of nuclear reactors, as well for reactivity determination as for on-line modelisation in order to detect eventual and unwanted changes in working operation is illustrated. It is dealt with the reactivity estimation using an a priori dynamical model under the hypothesis of one group of delayed neutrons (measurements were done with an ionisation chamber). The determination of the reactivity using such measurements appears as a nonlinear estimation procedure derived from a particular form of nonlinear filter. Observed inputs being demand of power and inside temperature, and output being the reactivity balance, a recursive algorithm is derived for the estimation of the parameters that define the actual behavior of the reactor. Example of treatment of real data is given [fr

  19. Exploring Quantitative Framework to Evaluate Nuclear Transparency

    International Nuclear Information System (INIS)

    Ha, Jeemin; Yim, Mansung; Park, Hyeon Seok

    2014-01-01

    In this work, a definition of nuclear transparency is elaborated and ways to represent a country's nuclear transparency are examined. For evaluating nuclear transparency, it is necessary to define three elements first; an information seeker who wants to see, an information seek whom an information seeker wants to see, and information related to nuclear materials and activities. The States with high capacity of civilian nuclear power had a tendency to follow IAEA safeguards agreements well. And it means that their levels of the transparency are relatively high. Besides, the data of international assurances is one of the good indicators to confirm States' transparency. The current study explored the use of two measures, IAEA safeguards and voluntary reporting as a way to represent nuclear transparency. Using these measures seemed to agree with the notion that nuclear transparency is important in the success of civilian nuclear power development

  20. Stochastic models and reliability parameter estimation applicable to nuclear power plant safety

    International Nuclear Information System (INIS)

    Mitra, S.P.

    1979-01-01

    A set of stochastic models and related estimation schemes for reliability parameters are developed. The models are applicable for evaluating reliability of nuclear power plant systems. Reliability information is extracted from model parameters which are estimated from the type and nature of failure data that is generally available or could be compiled in nuclear power plants. Principally, two aspects of nuclear power plant reliability have been investigated: (1) The statistical treatment of inplant component and system failure data; (2) The analysis and evaluation of common mode failures. The model inputs are failure data which have been classified as either the time type of failure data or the demand type of failure data. Failures of components and systems in nuclear power plant are, in general, rare events.This gives rise to sparse failure data. Estimation schemes for treating sparse data, whenever necessary, have been considered. The following five problems have been studied: 1) Distribution of sparse failure rate component data. 2) Failure rate inference and reliability prediction from time type of failure data. 3) Analyses of demand type of failure data. 4) Common mode failure model applicable to time type of failure data. 5) Estimation of common mode failures from 'near-miss' demand type of failure data

  1. Parameters for calculation of nuclear reactions of relevance to non-energy nuclear applications (Reference Input Parameter Library: Phase III). Summary report of the first research coordination meeting

    International Nuclear Information System (INIS)

    Capote Noy, R.

    2004-08-01

    A summary is given of the First Research Coordination Meeting on Parameters for Calculation of Nuclear Reactions of Relevance to Non-Energy Nuclear Applications (Reference Input Parameter Library: Phase III), including a critical review of the RIPL-2 file. The new library should serve as input for theoretical calculations of nuclear reaction data at incident energies up to 200 MeV, as needed for energy and non-energy modern applications of nuclear data. Technical discussions and the resulting work plan of the Coordinated Research Programme are summarized, along with actions and deadlines. Participants' contributions to the RCM are also attached. (author)

  2. Verification and validation of the safety parameter display system for nuclear power plant

    International Nuclear Information System (INIS)

    Zhang Yuanfang

    1993-05-01

    During the design and development phase of the safety parameter display system for nuclear power plant, a verification and validation (V and V) plan has been implemented to improve the quality of system design. The V and V activities are briefly introduced, which were executed in four stages of feasibility research, system design, code development and system integration and regulation. The evaluation plan and the process of implementation as well as the evaluation conclusion of the final technical validation for this system are also presented in detail

  3. Evaluation of Control Parameters for the Activated Sludge Process

    Science.gov (United States)

    Stall, T. Ray; Sherrard, Josephy H.

    1978-01-01

    An evaluation of the use of the parameters currently being used to design and operate the activated sludge process is presented. The advantages and disadvantages for the use of each parameter are discussed. (MR)

  4. Oxidation parameters of nuclear graphite for HTGR air-ingress

    International Nuclear Information System (INIS)

    Kim, E.S.; No, H.C.

    2004-01-01

    In order to investigate chemical behaviors of the graphite during an air-ingress accident in HTGR, the kinetic tests on nuclear graphite IG-110 were performed in chemical reaction dominant regime. In the present experiment, inlet gas flow rate ranged between 8 and 18 SLPM, graphite temperatures and oxygen mole fraction ranged from 540 to 630degC and from 3 to 30% respectively. The test section was made of a quartz tube having 75 mm diameter and 750 mm length and the test specimen machined to the size of 21 mm diameter and 30 mm length was supported at the center of it by the alumina rod. The 15 kW induction heater was installed around the outside of test section to heat the specimen and its temperature was measured by 2 infrared thermometers. The oxidation rate was calculated from the gas concentration analysis between inlet and outlet using NDIR (non-dispersive infrared) gas analyzer. As a result the activation energy (Ea) and the order of reaction (n) were determined within 95% confidence level and the qualitative characteristics of the two parameters were also widely investigated by experimental and analytical methods. (author)

  5. Genetic algorithm for nuclear data evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Arthur, Jennifer Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-02-02

    These are slides on genetic algorithm for nuclear data evaluation. The following is covered: initial population, fitness (outer loop), calculate fitness, selection (first part of inner loop), reproduction (second part of inner loop), solution, and examples.

  6. Japanese Evaluated Nuclear Data Library, version-3

    International Nuclear Information System (INIS)

    Shibata, Keiichi; Nakagawa, Tsuneo; Asami, Tetsuo

    1990-06-01

    The general purpose file of the third version of Japanese Evaluated Nuclear Data Library, JENDL-3, has been compiled by the JAERI Nuclear Data Center in cooperation with the Japanese Nuclear Data Committee. It contains neutron nuclear data for 171 nuclides which are needed for design of fission and fusion reactors and for shielding calculation. In the JENDL-3 evaluation, much effort was devoted to improve reliability of high-energy data for fusion application and to include gamma-ray production data. Theoretical calculations played an important role in achieving these purposes. A special method called simultaneous evaluation was adopted to determine important cross sections of fissile and fertile nuclides. This report presents a general description for the evaluation of light, medium-heavy and heavy nuclide data. Also given are the descriptive data for each nuclide contained in the File 1 part of JENDL-3. (author)

  7. Determination of nuclear tracks parameters on sequentially etched PADC detectors

    Science.gov (United States)

    Horwacik, Tomasz; Bilski, Pawel; Koerner, Christine; Facius, Rainer; Berger, Thomas; Nowak, Tomasz; Reitz, Guenther; Olko, Pawel

    Polyallyl Diglycol Carbonate (PADC) detectors find many applications in radiation protection. One of them is the cosmic radiation dosimetry, where PADC detectors measure the linear energy transfer (LET) spectra of charged particles (from protons to heavy ions), supplementing TLD detectors in the role of passive dosemeter. Calibration exposures to ions of known LET are required to establish a relation between parameters of track observed on the detector and LET of particle creating this track. PADC TASTRAK nuclear track detectors were exposed to 12 C and 56 Fe ions of LET in H2 O between 10 and 544 keV/µm. The exposures took place at the Heavy Ion Medical Accelerator (HIMAC) in Chiba, Japan in the frame of the HIMAC research project "Space Radiation Dosimetry-Ground Based Verification of the MATROSHKA Facility" (20P-240). Detectors were etched in water solution of NaOH with three different temperatures and for various etching times to observe the appearance of etched tracks, the evolution of their parameters and the stability of the etching process. The applied etching times (and the solution's concentrations and temperatures) were: 48, 72, 96, 120 hours (6.25 N NaOH, 50 O C), 20, 40, 60, 80 hours (6.25 N NaOH, 60 O C) and 8, 12, 16, 20 hours (7N NaOH, 70 O C). The analysis of the detectors involved planimetric (2D) measurements of tracks' entrance ellipses and mechanical measurements of bulk layer thickness. Further track parameters, like angle of incidence, track length and etch rate ratio were then calculated. For certain tracks, results of planimetric measurements and calculations were also compared with results of optical track profile (3D) measurements, where not only the track's entrance ellipse but also the location of the track's tip could be directly measured. All these measurements have been performed with the 2D/3D measurement system at DLR. The collected data allow to create sets of V(LET in H2 O) calibration curves suitable for short, intermediate and

  8. International evaluated neutron nuclear data libraries

    International Nuclear Information System (INIS)

    Liu Tingjin

    2001-01-01

    The current status of five major evaluated neutron nuclear data libraries in the world are introduced. They are ENDF/B-6 (U. S. A.), JENDL-3.2 (Japan), JEF-2.2 (Europe), CENDL-2.1 (China), BROND-2 (Russia). The developing trend of the international neutron evaluated nuclear data library is discussed. How to get and use these data for the domestic users is given

  9. ENSDF: The evaluated nuclear structure data file

    International Nuclear Information System (INIS)

    Martin, M.J.

    1986-01-01

    The structure, organization, and contents of the Evaluated Nuclear Structure Data File, ENSDF, will be discussed. This file summarizes the state of experimental nuclear structure data for all nuclei as determined from consideration of measurements reported world wide. Special emphasis will be given to the data evaluation procedures and consistency checks utilized at the input stage and to the retrieval capabilities of the system at the output stage

  10. Researches on nuclear criticality safety evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Okuno, Hiroshi; Suyama, Kenya; Nomura, Yasushi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-10-01

    For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)

  11. Researches on nuclear criticality safety evaluation

    International Nuclear Information System (INIS)

    Okuno, Hiroshi; Suyama, Kenya; Nomura, Yasushi

    2003-01-01

    For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)

  12. INPRO Methodology to evaluate the Mexico nuclear energy system

    International Nuclear Information System (INIS)

    Cruz S, R. R.; Martin del C, C.

    2016-09-01

    The International Atomic Energy Agency has developed the so-called International Project on Fuel Cycles and Innovative Nuclear Reactors (INPRO), in order to make nuclear energy available to meet the energy needs of the 21 century, in a sustainable way. One of the tasks of the project is the evaluation of the nuclear systems, to check whether they meet the objectives of the project and whether they are sustainable. This paper explains the rationale and general characteristics of the project in the evaluation of nuclear energy systems based on the concept of sustainable development. It describes the methodology developed to carry out this evaluation, divided into seven areas, such as economic, environmental, security, etc., which together make up the sustainable development of energy through nuclear systems. The economic area is analyzed and the evaluation criteria and parameters established by INPRO are discussed, in order to evaluate the Mexican nuclear energy system using Nest (software developed within the same project) as a tool to support the economic evaluation of nuclear systems. Based on the energy strategy proposed by the Energy Secretary of the Mexican Government which seeks to reduce the greenhouse gas emissions from the national electricity generation park, two types of reactor of currently available technology (A BWR and AP1000), were compared and these in turn with other alternative energy generation technologies, such as combined cycle, geothermal and wind plants. Also, the results of the application of the INPRO methodology are presented. Finally, the recommendations on actions that could lead the Mexican nuclear energy system towards sustainable development and conclusions on the application of the methodology to the Mexican case are mentioned. (Author)

  13. Evaluated Nuclear Structure Data File (ENSDF)

    International Nuclear Information System (INIS)

    Bhat, M.R.

    1991-01-01

    The Evaluated Nuclear Structure Data File (ENSDF), is maintained by the National Nuclear Data Center (NNDC) on behalf of the international Nuclear Structure and Decay Data (NSDD) network organized under the auspices of the International Atomic Energy Agency. ENSDF provides evaluated experimental nuclear structure and decay data for basic and applied research. The activities of the NSDD network, the publication of the evaluations, and their use in different applications are described. Since 1986, the ENSDF and related numeric and bibliographic data bases have been made available for on-line access. The current status of these data bases, and future plans to improve the on-line access to their contents are discussed. 8 refs., 4 tabs

  14. Average resonance parameters evaluation for actinides

    Energy Technology Data Exchange (ETDEWEB)

    Porodzinskij, Yu.V.; Sukhovitskij, E.Sh. [Radiation Physics and Chemistry Problems Inst., Minsk-Sosny (Belarus)

    1997-03-01

    New evaluated <{Gamma}{sub n}{sup 0}> and values for {sup 238}U, {sup 237}Np, {sup 243}Cm, {sup 245}Cm, {sup 246}Cm and {sup 241}Am nuclei in the resolved resonance region are presented. The applied method based on the idea that experimental resonance missing results in correlated changes of reduced neutron widths and level spacings distributions is discussed. (author)

  15. Virtual Acoustics: Evaluation of Psychoacoustic Parameters

    Science.gov (United States)

    Begault, Durand R.; Null, Cynthia H. (Technical Monitor)

    1997-01-01

    Current virtual acoustic displays for teleconferencing and virtual reality are usually limited to very simple or non-existent renderings of reverberation, a fundamental part of the acoustic environmental context that is encountered in day-to-day hearing. Several research efforts have produced results that suggest that environmental cues dramatically improve perceptual performance within virtual acoustic displays, and that is possible to manipulate signal processing parameters to effectively reproduce important aspects of virtual acoustic perception in real-time. However, the computational resources for rendering reverberation remain formidable. Our efforts at NASA Ames have been focused using a several perceptual threshold metrics, to determine how various "trade-offs" might be made in real-time acoustic rendering. This includes both original work and confirmation of existing data that was obtained in real rather than virtual environments. The talk will consider the importance of using individualized versus generalized pinnae cues (the "Head-Related Transfer Function"); the use of head movement cues; threshold data for early reflections and late reverberation; and consideration of the necessary accuracy for measuring and rendering octave-band absorption characteristics of various wall surfaces. In addition, a consideration of the analysis-synthesis of the reverberation within "everyday spaces" (offices, conference rooms) will be contrasted to the commonly used paradigm of concert hall spaces.

  16. Single parameter controls for nuclear criticality safety at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    Baker, J.S.; Peek, W.M.

    1995-01-01

    At the Oak Ridge Y-12 Plant, there are numerous situations in which nuclear criticality safety must be assured and subcriticality demonstrated by some method other than the straightforward use of the double contingency principle. Some cases are cited, and the criticality safety evaluation of contaminated combustible waste collectors is considered in detail. The criticality safety evaluation for combustible collectors is based on applying one very good control to the one controllable parameter. Safety can only be defended when the contingency of excess density is limited to a credible value based on process knowledge. No reasonable single failure is found that will result in a criticality accident. The historically accepted viewpoint is that this meets double contingency, even though there are not two independent controls on the single parameter of interest

  17. Automated approach to nuclear facility safeguards effectiveness evaluation

    International Nuclear Information System (INIS)

    1977-01-01

    Concern over the security of nuclear facilities has generated a need for a reliable, time efficient, and easily applied method of evaluating the effectiveness of safeguards systems. Such an evaluation technique could be used (1) by the Nuclear Regulatory Commission to evaluate a licensee's proposal, (2) to assess the security status of a system, or (3) to design and/or upgrade nuclear facilities. The technique should be capable of starting with basic information, such as the facility layout and performance parameters for physical protection components, and analyzing that information so that a reliable overall facility evaluation is obtained. Responding to this expressed need, an automated approach to facility safeguards effectiveness evaluation has been developed. This procedure consists of a collection of functional modules for facility characterization, critical path generation, and path evaluation combined into a continuous stream of operations. The technique has been implemented on an interactive computer-timesharing system and makes use of computer graphics for the handling and presentation of information. Using this technique a thorough facility evaluation can be made by systematically varying parameters that characterize the physical protection components of a facility according to changes in perceived adversary attributes and strategy, environmental conditions, and site status

  18. International nuclear fuel cycle evaluation (INFCE)

    International Nuclear Information System (INIS)

    Schlupp, C.

    1986-07-01

    The study describes and analyzes the structures, the procedures and decision making processes of the International Nuclear Fuel Cycle Evaluation (INFCE). INFCE was agreed by the Organizing Conference to be a technical and analytical study and not a negotiation. The results were to be transmitted to governments for their consideration in developing their nuclear energy policies and in international discussions concerning nuclear energy cooperation and related controls and safeguards. Thus INFCE provided a unique example for decision making by consensus in the nuclear world. It was carried through under mutual respect for each country's choices and decisions, without jeopardizing their respective fuel cycle policies or international co-operation agreements and contracts for the peaceful use of nuclear energy, provided that agreed safeguards are applied. (orig.)

  19. Nuclear power plant simulation facility evaluation methodology

    International Nuclear Information System (INIS)

    Haas, P.M.; Carter, R.J.; Laughery, K.R. Jr.

    1985-01-01

    A methodology for evaluation of nuclear power plant simulation facilities with regard to their acceptability for use in the US Nuclear Regulatory Commission (NRC) operator licensing exam is described. The evaluation is based primarily on simulator fidelity, but incorporates some aspects of direct operator/trainee performance measurement. The panel presentation and paper discuss data requirements, data collection, data analysis and criteria for conclusions regarding the fidelity evaluation, and summarize the proposed use of direct performance measurment. While field testing and refinement of the methodology are recommended, this initial effort provides a firm basis for NRC to fully develop the necessary methodology

  20. Evaluation of nuclear power plant operator's ability

    International Nuclear Information System (INIS)

    Wei Li; He Xuhong; Zhao Bingquan

    2004-01-01

    Based on the quantitative research on nuclear power plant (NPP) operator's psychological characteristics and performance, the Borda's method of fuzzy mathematics combined with the character of operator's task is used to evaluate their abilities. The result provides the reference for operator's reliability research and psychological evaluation. (author)

  1. Influence of various parameters on effectiveness of seismic base isolation of nuclear equipment

    International Nuclear Information System (INIS)

    Ebisawa, K.; Kameoka, H.; Takenouchi, I.; Kajiki, S.

    1995-01-01

    Authors developed a methodology and EBISA code for evaluating the applicability and the effectiveness of seismic base isolation of nuclear equipment. In order to investigate the influence of various parameters on the effectiveness of seismic base isolation, a sensitivity analysis was carried out for an emergency transformer with the base isolation devices. It was proved that seismic base isolation of equipment is very effective. This effectiveness can be influenced by the differences of the base isolation devices and the direction of the input seismic wave. (author). 7 refs., 3 figs., 3 tabs

  2. Practice Parameter for Child and Adolescent Forensic Evaluations

    Science.gov (United States)

    Journal of the American Academy of Child & Adolescent Psychiatry, 2011

    2011-01-01

    This Parameter addresses the key concepts that differentiate the forensic evaluation of children and adolescents from a clinical assessment. There are ethical issues unique to the forensic evaluation, because the forensic evaluator's duty is to the person, court, or agency requesting the evaluation, rather than to the patient. The forensic…

  3. Techniques used for charged particle nuclear data evaluation at CNDC

    International Nuclear Information System (INIS)

    Zhuang Youxiang; Sun Zuxun

    1993-01-01

    The methods and techniques used for Charged Particle Nuclear Data (CPND) evaluation at Chinese Nuclear Data Center (CNDC) are summarized, including compilation and evaluation of experimental data, nuclear reaction theory and model calculation, systematics research and comprehensive recommendation etc

  4. World Integrated Nuclear Evaluation System: Model documentation

    International Nuclear Information System (INIS)

    1991-12-01

    The World Integrated Nuclear Evaluation System (WINES) is an aggregate demand-based partial equilibrium model used by the Energy Information Administration (EIA) to project long-term domestic and international nuclear energy requirements. WINES follows a top-down approach in which economic growth rates, delivered energy demand growth rates, and electricity demand are projected successively to ultimately forecast total nuclear generation and nuclear capacity. WINES could be potentially used to produce forecasts for any country or region in the world. Presently, WINES is being used to generate long-term forecasts for the United States, and for all countries with commercial nuclear programs in the world, excluding countries located in centrally planned economic areas. Projections for the United States are developed for the period from 2010 through 2030, and for other countries for the period starting in 2000 or 2005 (depending on the country) through 2010. EIA uses a pipeline approach to project nuclear capacity for the period between 1990 and the starting year for which the WINES model is used. This approach involves a detailed accounting of existing nuclear generating units and units under construction, their capacities, their actual or estimated time of completion, and the estimated date of retirements. Further detail on this approach can be found in Appendix B of Commercial Nuclear Power 1991: Prospects for the United States and the World

  5. Recommended parameters for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities

    International Nuclear Information System (INIS)

    Li Hong; Fang Dong; Sun Chengzhi; Xiao Naihong

    2003-01-01

    A set of models and default parameters are recommended for effect assessment of radioactive airborne effluents under normal condition of nuclear facilities in order to standardize the environmental effect assessment of nuclear facilities, and to simplify the observation and investigation in early phase. The paper introduces the input data and default parameters used in the model

  6. Development of radionuclide parameter database on internal contamination in nuclear emergencies

    International Nuclear Information System (INIS)

    Zhao Li; Xu Cuihua; Li Wenhong; Su Xu

    2010-01-01

    Objective: To develop a radionuclide parameter database on internal contamination in nuclear emergencies. Methods: By researching the radionuclides composition discharged from different nuclear emergencies, the radionuclide parameters were achieved on physical decay, absorption and metabolism in the body from ICRP publications and some other publications. The database on internal contamination for nuclear incidents was developed by using MS Visual Studio 2005 C and MS Access programming language. Results: The radionuclide parameter database on internal contamination in nuclear emergency was established. Conclusions: The database may be very convenient for searching radionuclides and radionuclide parameter data discharged from different nuclear emergencies, which would be helpful to the monitoring and assessment and assessment of internal contamination in nuclear emergencies. (authors)

  7. Objective parameters for engine noise quality evaluation; Objektive Parameter zur Bewertung der Motorgeraeuschqualitaet

    Energy Technology Data Exchange (ETDEWEB)

    Graf, Bernhard; Brandl, Stephan [AVL List GmbH, Graz (Austria); Sontacchi, Alois [Univ. fuer Musik und Darstellende Kunst, Graz (Austria). Inst. fuer Elektronische Musik und Akustik; Girstmair, Josef [Kompetenzzentrum Das Virtuelle Fahrzeug, Graz (Austria). Gruppe Antriebsstrang Dynamik und Akustik

    2013-06-01

    Due to ongoing downsizing efforts and more stringent emission regulations, relevance of sound quality monitoring during engine and vehicle development is strongly increasing. Therefore AVL developed new sound quality parameters like CKI (Combustion Knocking Index) and HI (Harshness Index). Using these parameters sound quality can be objectively monitored, without subjective evaluations, online throughout the complete development process. (orig.)

  8. Evaluation of tomographic ISOCAM Park II gamma camera parameters using Monte Carlo method

    International Nuclear Information System (INIS)

    Oramas Polo, Ivón

    2015-01-01

    In this paper the evaluation of tomographic ISOCAM Park II gamma camera parameters was performed using the Monte Carlo code SIMIND. The parameters uniformity, resolution and contrast were evaluated by Jaszczak phantom simulation. In addition the qualitative assessment of the center of rotation was performed. The results of the simulation are compared and evaluated against the specifications of the manufacturer of the gamma camera and taking into account the National Protocol for Quality Control of Nuclear Medicine Instruments of the Cuban Medical Equipment Control Center. A computational Jaszczak phantom model with three different distributions of activity was obtained. They can be used to perform studies with gamma cameras. (author)

  9. The Jeff evaluated nuclear data project

    Energy Technology Data Exchange (ETDEWEB)

    Koning, A.J.; Duijvestijn, M.C.; Hogenbirk, A.; Van der Marck, S.C.; Avrigeanu, M.; Avrigeanu, V.; Batistoni, P.; Pillon, M.; Bauge, E.; Bersillon, O.; Dos-Santos-Uzarralde, P.; Lopez Jimenez, M.J.; Morillon, B.; Romain, P.; Be, M.M.; Duchemin, B.; Huynh, T.D.; Jouanne, C.; Mounier, C.; Bem, P.; Bernard, D.; Bouland, O.; Courcelle, A.; Dupont, E.; Jacqmin, R.; Litaize, O.; Noguere, G.; Saint Jean, C. de; Santamarina, A.; Serot, O.; Sublet, J.Ch.; Bidaud, A.; Dean, C.J.; Perry, R.J.; Duhamel, I.; Nouri, A.; Gunsing, F.; Ridikas, D.; Fischer, U.; Leichtle, D.; Pereslavtsev, P.; Simakov, S.; Forrest, R.A.; Haeck, W.; Henriksson, H.; Kodeli, I.; Nordborg, C.; Rugama, Y.; Sartori, E.; Keinert, J.; Mattes, M.; Kellett, M.A.; Nichols, A.L.; Kopecky, J.; Leeb, H.; Leppanen, J.; Menapace, E.; Pescarini, M.; Mills, R.W.; Perel, R.L.; Plompen, A.J.M.; Rullhusen, P.; Seidel, K.; Tagesen, S.; Vonach, H.; Trkov, A

    2008-07-01

    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. JEFF-3.1 comprises a significant update of actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library JEFF-3.1/A, the decay data and fission yield sub-libraries, and fusion-related data files from the EFF project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory and shielding of thermal and fast systems. Compared with earlier releases, JEFF-3.1 provides improved performance with respect to a variety of scientific and industrial applications. Following on from the public release of JEFF-3.1, the French nuclear power industry has selected this suite of nuclear applications libraries for inclusion in their production codes. (authors)

  10. The Jeff evaluated nuclear data project

    International Nuclear Information System (INIS)

    Koning, A.J.; Duijvestijn, M.C.; Hogenbirk, A.; Van der Marck, S.C.; Avrigeanu, M.; Avrigeanu, V.; Batistoni, P.; Pillon, M.; Bauge, E.; Bersillon, O.; Dos-Santos-Uzarralde, P.; Lopez Jimenez, M.J.; Morillon, B.; Romain, P.; Be, M.M.; Duchemin, B.; Huynh, T.D.; Jouanne, C.; Mounier, C.; Bem, P.; Bernard, D.; Bouland, O.; Courcelle, A.; Dupont, E.; Jacqmin, R.; Litaize, O.; Noguere, G.; Saint Jean, C. de; Santamarina, A.; Serot, O.; Sublet, J.Ch.; Bidaud, A.; Dean, C.J.; Perry, R.J.; Duhamel, I.; Nouri, A.; Gunsing, F.; Ridikas, D.; Fischer, U.; Leichtle, D.; Pereslavtsev, P.; Simakov, S.; Forrest, R.A.; Haeck, W.; Henriksson, H.; Kodeli, I.; Nordborg, C.; Rugama, Y.; Sartori, E.; Keinert, J.; Mattes, M.; Kellett, M.A.; Nichols, A.L.; Kopecky, J.; Leeb, H.; Leppanen, J.; Menapace, E.; Pescarini, M.; Mills, R.W.; Perel, R.L.; Plompen, A.J.M.; Rullhusen, P.; Seidel, K.; Tagesen, S.; Vonach, H.; Trkov, A.

    2008-01-01

    The status of the Joint Evaluated Fission and Fusion file (JEFF) is described. JEFF-3.1 comprises a significant update of actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library JEFF-3.1/A, the decay data and fission yield sub-libraries, and fusion-related data files from the EFF project. The revisions were motivated by the availability of new measurements, modelling capabilities and trends from integral experiments. Validations have been performed, mainly for criticality, reactivity temperature coefficients, fuel inventory and shielding of thermal and fast systems. Compared with earlier releases, JEFF-3.1 provides improved performance with respect to a variety of scientific and industrial applications. Following on from the public release of JEFF-3.1, the French nuclear power industry has selected this suite of nuclear applications libraries for inclusion in their production codes. (authors)

  11. Calculation of nuclear parameters for some heavy isotopes

    International Nuclear Information System (INIS)

    Corcuera, R.P.; Pinheiro, A.M.B.S.

    1981-01-01

    Some integrals are calculated using different weighting functions, the basic data come from two different nuclear data libraries, ENDF/B IV and ENDL/78. Significant discrepancies are found when are or the other lirary are used. (author) [pt

  12. Computer system for nuclear power plant parameter display

    International Nuclear Information System (INIS)

    Stritar, A.; Klobuchar, M.

    1990-01-01

    The computer system for efficient, cheap and simple presentation of data on the screen of the personal computer is described. The display is in alphanumerical or graphical form. The system can be used for the man-machine interface in the process monitoring system of the nuclear power plant. It represents the third level of the new process computer system of the Nuclear Power Plant Krsko. (author)

  13. Atomic parity nonconservation: Electroweak parameters and nuclear structure

    International Nuclear Information System (INIS)

    Pollock, S.J.; Fortson, E.N.; Wilets, L.

    1992-01-01

    There have been suggestions to measure atomic parity nonconservation (PNC) along an isotopic chain, by taking ratios of observables in order to cancel complicated atomic-structure effects. Precise atomic PNC measurements could make a significant contribution to tests of the standard model at the level of one-loop radiative corrections. However, the results also depend upon certain features of nuclear structure, such as the spatial distribution of neutrons in the nucleus. To examine the sensitivity to nuclear structure, we consider the case of Pb isotopes using various recent relativistic and nonrelativistic nuclear model calculations. Contributions from nucleon internal weak structure are included, but found to be fairly negligible. The spread among present models in predicted sizes of nuclear-structure effects may preclude using Pb isotope ratios to test the standard model at better than a 1% level, unless there are adequate independent tests of the nuclear models by various alternative strong and electroweak nuclear probes. On the other hand, sufficiently accurate atomic PNC experiments would provide a unique method to measure neutron distributions in heavy nuclei

  14. Methods of control of inaccuracy in calculation of nuclear power plant decommissioning parameters - 16383

    International Nuclear Information System (INIS)

    Ondra, Frantisek; Daniska, Vladimir; Rehak, Ivan; Necas, Vladimir

    2009-01-01

    The aim of the article is a development of analytical methodology for evaluation of input data inaccuracies impact on calculation of cost and other output decommissioning parameters. This methodology is based on analytical model calculations using the OMEGA code and taking into account the probability of input data inaccuracies occurrence also. To achieve about mentioned aim, the article identifies possible sources of input data inaccuracies and analyzes their level of impact on output parameters. Then the methodology for calculation of input parameters inaccuracies impact is developed, based on analytical model calculation. The model calculation takes into consideration output parameters impact on cost and other decommissioning output parameters in analytical way. The methodology used in model calculations is original, more over it implements the international standardized structure (IAEA, OECD/NEA, EC) [6] of decommissioning cost for the first time. A probabilistic occurrence of input data inaccuracies is taken into consideration and implemented in the methodology developed. A correction factors matrix for evaluation of input data inaccuracies impact on decommissioning output parameters is set up. The matrix contains parameters based on model calculations using the proposed methodology. Finally the methodology for application of correction factor matrix is proposed and tested; the methodology is used for calculation of contingency in the standardized structure which reflected the level of input data inaccuracies. The cost for individual decommissioning projects for common nuclear power plants are in the range 300 - 500 mil. EUR. Contingencies are from 10% to 30%, depending on the level of detailed during preparation of decommissioning projects. A implementation about mentioned methodology in the OMEGA code improves the accuracy of contingency. Consequently it makes calculated contingency more trustworthy and makes calculated decommissioning cost closer to reality

  15. Benchmark comparisons of evaluated nuclear data files

    International Nuclear Information System (INIS)

    Resler, D.A.; Howerton, R.J.; White, R.M.

    1994-05-01

    With the availability and maturity of several evaluated nuclear data files, it is timely to compare the results of integral tests with calculations using these different files. We discuss here our progress in making integral benchmark tests of the following nuclear data files: ENDL-94, ENDF/B-V and -VI, JENDL-3, JEF-2, and BROND-2. The methods used to process these evaluated libraries in a consistent way into applications files for use in Monte Carlo calculations is presented. Using these libraries, we are calculating and comparing to experiment k eff for 68 fast critical assemblies of 233,235 U and 239 Pu with reflectors of various material and thickness

  16. Site evaluation for nuclear installations. Safety requirements

    International Nuclear Information System (INIS)

    2003-01-01

    This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Siting, which was issued in 1988 as Safety Series No. 50-C-S (Rev. 1). It takes account of developments relating to site evaluations for nuclear installations since the Code on Siting was last revised. These developments include the issuing of the Safety Fundamentals publication on The Safety of Nuclear Installations, and the revision of various safety standards and other publications relating to safety. Requirements for site evaluation are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements change with these advances and this publication reflects the present consensus among States. This Safety Requirements publication was prepared under the IAEA programme on safety standards for nuclear installations. It establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references provide recommendations on how to meet the requirements established in this Safety Requirements publication. The objective of this publication is to establish the requirements for the elements of a site evaluation for a nuclear installation so as to characterize fully the site specific conditions pertinent to the safety of a nuclear installation. The purpose is to establish requirements for criteria, to be applied as appropriate to site and site-installation interaction in operational states and accident conditions, including those that could lead to emergency measures for: (a) Defining the extent of information on a proposed site to be presented by the applicant; (b) Evaluating a proposed site to ensure that the site

  17. Program of evaluations for nuclear data centers

    International Nuclear Information System (INIS)

    Cunha Menezes Filho, A. da.

    1980-01-01

    Standard problems for evaluating basic data libraries of multigroup constant generation, and codes for calculating integral parameters existing or will exist in the near future in the advanced study division (EAV), are defined. (M.C.K.) [pt

  18. Computer program system for evaluation of FP nuclear data for JENDL. Smooth part

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Watanabe, Takashi; Iijima, Shungo

    1997-12-01

    This report describes computer programs used to evaluate nuclear data of fission product (FP) nuclides stored in an evaluated nuclear data library JENDL, especially in the smooth part above the resonance region. Many programs were used for determination of nuclear model parameters, calculation of nuclear data, handling of experimental and/or calculated data, and so on. Among them, reported here are programs for determination of level density parameters (ENSDFRET, LVLPLOT, LEVDES), for making sets of JCL and input data for the theoretical calculation program CASTHY (JOBSETTER, INDES/CASTHY), and for conversion of format of CASTHY output files to the ENDF format (CTOB2). (author). 51 refs.

  19. Problems of nuclear power plant safety evaluation

    International Nuclear Information System (INIS)

    Suchomel, J.

    1977-01-01

    Nuclear power plant safety is discussed with regard to external effects on the containment and to the human factor. As for external effects, attention is focused on shock waves which may be due to explosions or accidents in flammable material transport and storage, to missiles, and to earthquake effects. The criteria for evaluating nuclear power plant safety in different countries are shown. Factors are discussed affecting the reliability of man with regard to his behaviour in a loss-of-coolant accident in the power plant. Different types of PWR containments and their functions are analyzed, mainly in case of accident. Views are discussed on the role of destructive accidents in the overall evaluation of fast reactor safety. Experiences are summed up gained with the operation of WWER reactors with respect to the environmental impact of the nuclear power plants. (Z.M.)

  20. Investigation of fuel lattice pitch changes influence on reactor performance through evaluate the neutronic parameters

    International Nuclear Information System (INIS)

    Zareian Ronizi, F.; Fadaei, A.H.; Setayeshi, S.; Shahidi, A.R.

    2015-01-01

    Highlights: • One of the most complex issues that Nu-engineers deal with is the design of NR core. • Numerous factors in nuclear core design depend on Fuel-to-Moderator volume ratio. • Aim of this research is to investigate RX performance for different lattice pitches. - Abstract: Nuclear reactor core design is one of the most complex issues that nuclear engineers deal with. The number and complexity of effective parameters and their impact on reactor design, which makes the problem difficult to solve, require precise knowledge of these parameters and their influence on the reactor operation. Numerous factors in a nuclear reactor core design depend on the Fuel-to-Moderator volume ratio, V F /V M , in a fuel cell. This ratio can be modified by changing the lattice pitch which is the thickness of water channels between fuels plates while keeping fuel slab dimensions fixed. Cooling and moderating properties of water are affected by such a change in a reactor core, and hence some parameters related to these properties might be changed. The aim of this research is to provide the suitable knowledge for nuclear core designing. To reach this goal, the first operating core of Tehran Research Reactor (TRR) with different lattice pitches is simulated, and the effect of different lattice pitches on some parameters such as effective multiplication factor (K eff ), reactor life time, distribution of neutron flux and power density in the core, as well as moderator temperature and density coefficient of reactivity are evaluated. The nuclear reactor analysis code, MTR-PC package is employed to carry out the considered calculation. Finally, the results are presented in some tables and graphs that provide useful information for nuclear engineers in the nuclear reactor core design

  1. Evaluation of Body Weight and Other Linear Parameters of Marshall ...

    African Journals Online (AJOL)

    This study was designed to evaluate the body weight and other linear parameters of Marshall Broiler for repeatability estimates. A total of one hundred (100) broiler chickens (Marshall) was used in estimating the repeatability of body weight and linear parameters of day old from 2 to 8 weeks of age. Body weight (BW) and ...

  2. Evaluation of physico-chemical parameters of agricultural soils ...

    African Journals Online (AJOL)

    Evaluation of physico-chemical parameters of agricultural soils irrigated by the waters of the hydrolic basin of Sebou River and their influences on the transfer of trace elements into sugar crops (the case of sugar cane)

  3. Performance Evaluation and HaematologicalParameters of West ...

    African Journals Online (AJOL)

    Performance Evaluation and HaematologicalParameters of West African Dwarf Goats Fed Diet Containing Graded Level of Raw and Fermented Malted Sorghum ... influenced white blood cell count (WBC), lymphocytes, monocytes, basophil and mean corpuscular haemoglobin concentration across the dietary treatments.

  4. JUPITER PROJECT - JOINT UNIVERSAL PARAMETER IDENTIFICATION AND EVALUATION OF RELIABILITY

    Science.gov (United States)

    The JUPITER (Joint Universal Parameter IdenTification and Evaluation of Reliability) project builds on the technology of two widely used codes for sensitivity analysis, data assessment, calibration, and uncertainty analysis of environmental models: PEST and UCODE.

  5. Structural integrity evaluation of nuclear piping cracket

    International Nuclear Information System (INIS)

    Cadiz Deleito, J.C.

    1985-01-01

    The methodology to evaluation of cracks in nuclear piping is exposed. Linear elastic fracture mechanic is used to prediction of growing crack and the net section collapse theory compared with acceptation criteria of both ASME III and ASME XI code. A case allowable under ASME XI criteria is analysed under ASME III requirements. Consideration must be given to local phenomenon in crack area and local stress evaluated and compared with ASME III acceptation criteria. (author)

  6. Study of excitation energy dependence of nuclear level density parameter

    International Nuclear Information System (INIS)

    Mohanto, G.; Nayak, B.K.; Saxena, A.

    2016-01-01

    In the present study, we have populated CN by fusion reaction and excitation energy of the intermediate nuclei is determined after first chance α-emission to investigate excitation energy dependence of the NLD parameter. Evaporated neutron spectra were measured following alpha evaporation for obtaining NLD parameter for the reaction 11 B + 197 Au, populating CN 208 Po. This CN after evaporating an α-particle populates intermediate nucleus 204 Pb. The 204 Pb has magic number of Z=82. Our aim is to study the excitation energy dependence of NLD parameter for closed shell nuclei

  7. Status report [Parameters for calculation of nuclear reactions of relevance to non-energy nuclear applications

    International Nuclear Information System (INIS)

    Koning, A.

    2008-01-01

    Full text: Masses: Adopted Goriely HFB masses in TALYS as theoretical default instead of Moeller. Audi-Wapstra, Moeller and HFB masses tested formally with TALYS. Levels. Adopted latest discrete level update (2006) by Belgya (as sent by Capote) in TALYS. Tested with TALYS. Resonances. Adopted RIPL-2 D0 collection in TALYS. Tested by TALYS. Optical model. Coordinated Optical model segment for RIPL-3. Adopted Soukhovitskii CC potential as default for actinides. Covariances: Confirmed OMP parameter uncertainties from last meeting. Level density. Produced consistent set of level density parameters for CTM, BFM, GSM and HFM. Local models (per nucleus) and global models (systematics). With and without effective collective enhancement. Included and tested with TALYS Gamma-ray strength. Adopted Goriely HFB strength function tables as option (not default) in TALYS. Both formally tested and validated with TALYS. Fission. Adopted Sin-Capote WKB approximation in TALYS as option for fission calculations. Formally tested. RIPL-2/3 validation. Very extensive formal tests and validation procedures with TALYS. MONKEY code for random input files (has found RIPL errors in the past). Automatic comparison with all available EXFOR cross section data (for level density study). Started work on global parameter uncertainties (for covariances). SALTY nuclear data library (final version under construction): - 60 MeV n,g,p,d,t,h,a activation files for 1200 nuclides - 200 MeV n,g,p,d,t,h,a transport files for 250 nuclides RIPL is automatically being used by all TALYS users (and TALYS-related publications). TALYS-1.0 release in December 2007 (delay because of level densities). (author)

  8. Evaluation of neutron nuclear data for 243Am

    International Nuclear Information System (INIS)

    Igarasi, Sin-iti; Nakagawa, Tsuneo

    1977-06-01

    Evaluation of neutron nuclear data for 243 Am was performed below 16 MeV. The energy region above 250 eV was separated from the lower region where the resonance parameters were given. Evaluation was made to select suitable resonance parameters, and thermal values of the capture and fission cross sections were obtained with the adopted resonance parameters. An average fission width was assumed to bridge the cross sections at 0.0253 eV and above 250 eV. Using a semi-empirical formula, the fission cross section was reproduced above 250 eV. Optical and statistical model calculations were made in order to obtain the total, capture, inelastic and elastic scattering, and (n,2n) reaction cross sections. (auth.)

  9. Evaluation of self-interaction parameters from binary phase diagrams

    International Nuclear Information System (INIS)

    Ellison, T.L.

    1977-10-01

    The feasibility of calculating Wagner self-interaction parameters from binary phase diagrams was examined. The self-interaction parameters of 22 non-ferrous liquid solutions were calculated utilizing an equation based on the equality of the chemical potentials of a component in two equilibrium phases. Utilization of the equation requires the evaluation of the first and second derivatives of various liquidus and solidus data at infinite dilution of the solute component. Several numerical methods for evaluating the derivatives of tabular data were examined. A method involving power series curve fitting and subsequent differentiation of the power series was found to be the most suitable for the interaction parameter calculations. Comparison of the calculated self-interaction parameters with values obtained from thermodynamic measurements indicates that the Wagner self-interaction parameter can be successfully calculated from binary phase diagrams

  10. Nuclear interactive evaluations on distributed processors

    International Nuclear Information System (INIS)

    Dix, G.E.; Congdon, S.P.

    1988-01-01

    BWR [boiling water reactor] nuclear design is a complicated process, involving trade-offs among a variety of conflicting objectives. Complex computer calculations and usually required for each design iteration. GE Nuclear Energy has implemented a system where the evaluations are performed interactively on a large number of small microcomputers. This approach minimizes the time it takes to carry out design iterations even through the processor speeds are low compared with modern super computers. All of the desktop microcomputers are linked to a common data base via an ethernet communications system so that design data can be shared and data quality can be maintained

  11. Evaluation of design parameters in soil-structure systems through artificial intelligence

    International Nuclear Information System (INIS)

    Cremonini, M.G.; Vardanega, C.; Parvis, E.

    1989-01-01

    This study refers to development of an artificial intelligence tool to evaluate design parameters for a soil-structure system as the foundations of Class 1 buildings of a nuclear power plant (NPP). This is based on an expert analysis of a large amount of information, collected during a comprehensive program of site investigations and laboratory tests and stored on a computer data-bank. The methodology comprises the following steps: organization of the available information on the site characteristics in a data-base; implementation and extensive use of a specific knowledge based expert system (KBES) devoted to both the analysis, interpretation and check of the information in the data-base, and to the evaluation of the design parameters; determination of effective access criteria to the data-base, for purposes of reordering the information and extracting design properties from a large number of experimental data; development of design profiles for both index properties and strength/strain parameters; and final evaluation of the design parameters. Results are obtained in the form of: local and general site stratigraphy; summarized soil index properties, detailing the site setting; static and dynamic stress-strain parameters, G/G max behavior and damping factors; condolidation parameters and OCR ratio; spatial distribution of parameters on site area; identification of specific local conditions; and cross correlation of parameters, thus covering the whole range of design parameters for NPP soil-structure systems

  12. Evaluation of Nuclear Hydrogen Production System

    International Nuclear Information System (INIS)

    Park, Won Seok; Park, C. K.; Park, J. K. and others

    2006-04-01

    The major objective of this work is tow-fold: one is to develop a methodology to determine the best VHTR types for the nuclear hydrogen demonstration project and the other is to evaluate the various hydrogen production methods in terms of the technical feasibility and the effectiveness for the optimization of the nuclear hydrogen system. Both top-tier requirements and design requirements have been defined for the nuclear hydrogen system. For the determination of the VHTR type, a comparative study on the reference reactors, PBR and PBR, was conducted. Based on the analytic hierarchy process (AHP) method, a systematic methodology has been developed to compare the two VHTR types. Another scheme to determine the minimum reactor power was developed as well. Regarding the hydrogen production methods, comparison indices were defined and they were applied to the IS (Iodine-Sulfur) scheme, Westinghouse process, and the, high-temperature electrolysis method. For the HTE, IS, and MMI cycle, the thermal efficiency of hydrogen production were systematically evaluated. For the IS cycle, an overall process was identified and the functionality of some key components was identified. The economy of the nuclear hydrogen was evaluated, relative to various primary energy including natural gas coal, grid-electricity, and renewable. For the international collaborations, two joint research centers were established: NH-JRC between Korea and China and NH-JDC between Korea and US. Currently, several joint researches are underway through the research centers

  13. Sensitivity analysis of parameters important to nuclear criticality safety of Castor X/28F spent nuclear fuel cask

    Energy Technology Data Exchange (ETDEWEB)

    Leotlela, Mosebetsi J. [Witwatersrand Univ., Johannesburg (South Africa). School of Physics; Koeberg Operating Unit, Johannesburg (South Africa). Regulations and Licensing; Malgas, Isaac [Koeberg Nuclear Power Station, Duinefontein (South Africa). Nuclear Engineering Analysis; Taviv, Eugene [ASARA consultants (PTY) LTD, Johannesburg (South Africa)

    2015-11-15

    In nuclear criticality safety analysis it is essential to ascertain how various components of the nuclear system will perform under certain conditions they may be subjected to, particularly if the components of the system are likely to be affected by environmental factors such as temperature, radiation or material composition. It is therefore prudent that a sensitivity analysis is performed to determine and quantify the response of the output to variation in any of the input parameters. In a fissile system, the output parameter of importance is the k{sub eff}. Therefore, in attempting to prevent reactivity-induced accidents, it is important for the criticality safety analyst to have a quantified degree of response for the neutron multiplication factor to perturbation in a given input parameter. This article will present the results of the perturbation of the parameters that are important to nuclear criticality safety analysis and their respective correlation equations for deriving the sensitivity coefficients.

  14. Utilities' nuclear fuel economic evaluation methods

    International Nuclear Information System (INIS)

    Sonz, L.A.

    1987-01-01

    This paper presents the typical perceptions, methods, considerations, and procedures used by an operating electric utility in the economic evaluation of nuclear fuel preparation and utilization scenarios. The means given are probably not an exclusive review of those available, but are the author's recollection of systems employed to select and recommend preferable courses of action. Economic evaluation of proposed nuclear fuel scenarios is an important, but not exclusive, means of deciding on corporate action. If the economic evaluation is performed and coordinated with the other corporate considerations, such as technical and operational ability, electrical system operations management, tax effects, capital management, rates impact, etc., then the resultant recommendation may be employed to the benefit of the customers and, consequently, to the corporation

  15. Evaluation of nuclear data of 244Pu and 237Pu

    International Nuclear Information System (INIS)

    Nakagawa, Tsuneo; Konshin, V.A.

    1995-10-01

    The evaluation of nuclear data for 244 Pu and 237 Pu was made in the neutron energy region from 10 -5 eV to 20 MeV. For the both nuclides, the total, elastic and inelastic scattering, fission, capture, (n,2n) and (n,3n) reaction cross sections were evaluated on the basis of theoretical calculation. The resonance parameters were given for 244 Pu. The angular and energy distributions of secondary neutrons were also estimated for the both nuclides. The results were compiled in the ENDF-5 format and will be adopted in JENDL Actinoid File. (author)

  16. Evaluation of neutron nuclear data for 249Cf

    International Nuclear Information System (INIS)

    Zhou Delin; Yu Baosheng; Yuan Hanrong; Liu Tong; Zhang Jin; Su Zongdi; Yan Shiwei; Wang Cuilan; Zhang Jingshang

    1992-01-01

    A complete set of neutron nuclear data from 10 -5 eV to 20 MeV in ENDF/B-6 format has been evaluated for 249 Cf based on measured data, systematics predications and model theory calculations. The evaluated quantities are the total, elastic and inelastic scattering, fission, capture, (n,2n), (n,3n) reaction cross sections, the resolved and unresolved resonance parameters, the angular and energy distributions of emitted neutrons and the average number of neutrons emitted per fission. The numerical data are available in ENDF/B-6 format

  17. Evaluation of Nuclear Data for Nuclear R and D Projects

    International Nuclear Information System (INIS)

    Chang, J. H.; Lee, Y. O.; Gil, C. S. and others

    2005-04-01

    Nuclear structure database, neutron data, charged particle data, and high energy service were improved and the libraries of WIMSD-5B, HELIOS, KASHIL-E6 were updated in response to the relevant users' requests. Measured resonance data, 19 nuclides for high burn-up fuel, isotopes for the thorium cycle were evaluated. Gamma production cross sections for underground resource exploration and for the development of in-core detector were also evaluated. The computer code system for theoretical model calculation was improved for the high energy nuclear data and, then applied to the evaluation for the accelerator and space applications. For the production of radioisotope, 'KAERI Charged Particle Cross Section Library' was published. Various libraries such as for MCNP4C, WIMSD-5, fast reactor, shielding, fission product burnup, and reactor benchmark were generated, and a code system for neutron and charged particle transport simulation was installed and their library production system was developed. Neutron capture cross sections were measured using facilities in Kyoto Univ. and TIT of Japan, and in Dubna, Russia. The TOF facility at PAL was upgraded and measurements were performed for 12 samples. Fast neutron measurement system was designed and built in the VDG facility, and its characteristics were also estimated

  18. Convective parameters in fuel elements for research nuclear reactors

    International Nuclear Information System (INIS)

    Lopez Martinez, C.D.

    1992-01-01

    The study of a prototype for the simulation of fuel elements for research nuclear reactors by natural convection in water is presented in this paper. This project is carry out in the thermofluids laboratory of National Institute of Nuclear Research. The fuel prototype has already been test for natural convection in air, and the first results in water are presented in this work. In chapter I, a general description of Triga Mark III is made, paying special atention to fuel-moderator components. In chapter II and III an approach to convection subject in its global aspects is made, since the intention is to give a general idea of the events occuring around fuel elements in a nuclear reactor. In chapter II, where an emphasis on forced convection is made, some basic concepts for forced convection as well as for natural convection are included. The subject of flow through cylinders is annotated only as a comparative reference with natural convection in vertical cylinders, noting the difference between used correlations and the involved variables. In chapter III a compilation of correlation found in the bibliography about natural convection in vertical cylinders is presented, since its geometry is the more suitable in the analysis of a fuel rod. Finally, in chapter IV performed experiments in the test bench are detailed, and the results are presented in form of tables and graphs, showing the used equations for the calculations and the restrictions used in each case. For the analysis of the prototypes used in the test bench, a constant and uniform flow of heat in the whole length of the fuel rod is considered. At the end of this chapter, the work conclusions and a brief explanation of the results are presented (Author)

  19. Evaluating the benefits of nuclear cardiology

    International Nuclear Information System (INIS)

    Maisey, M.

    1996-01-01

    This paper reviews the role of nuclear cardiology in the context of health care evaluation and resource utilisation. Nuclear cardiology procedures are used to detect disease, to define the extent of disease, to predict the outcome of therapy and to monitor the response to treatment. The evaluation of effectiveness will depend on the role for which the tests are being used. The evaluation of diagnostic tests most commonly follows the five level Fineberg classification. I) Technical capacity; II) diagnostic accuracy; III) diagnostic impact; IV) therapeutic impact; V) patient outcome. Tests may succeed or fail at each of these hierarchical levels. In addition to the clinical impact which is evaluated, the appropriate use of health care resources has to be considered , i.e. the cost effectiveness of the investigation. For this the costs of diagnosis and treatment in the resources used, together with the direct cost on the patient and patient carers needs to be considered. In addition to these direct costs to the community and to the patient and the carers the secondary downstream costs and opportunity costs have to be taken into account. The common methods for assessing the costs and benefits include cost minimization, cost effectiveness, cost utility, and cost benefit studies. The advantage and appropriate use of these methods are reviewed. There are seven clinical methods for evaluating diagnostics tests in nuclear cardiology which are: I) Case reports; II) consensus studies; III) databases; IV) management impact studies; V)modeling techniques; VI) management impact studies; VII) randomized control trial. Each of these has a role with advantages and disadvantages which are reviewed. It is no long sufficient to investigate the usefulness of a diagnostic test used in nuclear cardiology in isolation but it as to be within the context of the health care system and the resource used

  20. New nuclear data evaluations for Ca and Sc isotopes

    International Nuclear Information System (INIS)

    Koning, Arjan; Duijvestijn, Marieke

    2007-01-01

    New ENDF-6 formatted nuclear data libraries are presented for 40,42,43,44,46,48 Ca and 45 Sc, for incident neutrons and protons. Apart from the resonance range, which we have adopted from the best available source in existing libraries, the nuclear data evaluations are completely revised in the 0-20MeV energy range, and, moreover, extend up to 200 MeV. This collection of isotopic evaluations is created by using the nuclear model code TALYS with a consistent set of input parameters for all isotopes. The most important nuclear reaction models needed for our data files are described. We have intended to make these evaluations complete in their description of reaction channels and use a consistent method to store the data in ENDF-6 format, which include cross sections, angular distributions, double-differential spectra, discrete and continuum photon production cross sections, and residual production (activation) cross sections including isomers. It is shown that the data present in our libraries give an improved agreement with the existing basic experimental data. (author)

  1. A nuclear radiation multi-parameter measurement system based on pulse-shape sampling

    International Nuclear Information System (INIS)

    Qiu Xiaolin; Fang Guoming; Xu Peng; Di Yuming

    2007-01-01

    In this paper, A nuclear radiation multi-parameter measurement system based on pulse-shape sampling is introduced, including the system's characteristics, composition, operating principle, experiment data and analysis. Compared with conventional nuclear measuring apparatus, it has some remarkable advantages such as the synchronous detection using multi-parameter measurement in the same measurement platform and the general analysis of signal data by user-defined program. (authors)

  2. Propagation of uncertainties from basic data to key parameters of nuclear reactors

    International Nuclear Information System (INIS)

    Kodeli, I.

    2010-01-01

    The author reports the development of a set of computing software (SUSD3D) and of libraries of nuclear data covariance matrices to assess sensitivities of parameters with respect to basic nuclear data, and the corresponding uncertainties, notably for radiation transport for which uncertainty has various origins: reactivity coefficients or neutron and gamma ray flows. He reports the application to fusion and fission reactors

  3. Evaluation of Terminated Nuclear Material Licenses

    International Nuclear Information System (INIS)

    Spencer, K.M.; Zeighami, E.A.

    1999-01-01

    This report presents the results of a six-year project that reviewed material licenses that had been terminated during the period from inception of licensing until approximately late-1994. The material licenses covered in the review project were Part 30, byproduct material licenses; Part 40, source material licenses; and Part 70, special nuclear material licenses. This report describes the methodology developed for the project, summarizes the findings of the license file inventory process, and describes the findings of the reviews or evaluations of the license files. The evaluation identified nuclear material use sites that need review of the licensing material or more direct follow-up of some type. The review process also identified licenses authorized to possess sealed sources for which there was incomplete or missing documentation of the fate of the sources

  4. An optimization method for parameters in reactor nuclear physics

    International Nuclear Information System (INIS)

    Jachic, J.

    1982-01-01

    An optimization method for two basic problems of Reactor Physics was developed. The first is the optimization of a plutonium critical mass and the bruding ratio for fast reactors in function of the radial enrichment distribution of the fuel used as control parameter. The second is the maximization of the generation and the plutonium burnup by an optimization of power temporal distribution. (E.G.) [pt

  5. Calculation of nuclear level density parameters of some light deformed medical radionuclides using collective excitation modes of observed nuclear spectra

    International Nuclear Information System (INIS)

    Okuducu, S.; Sarac, H.; Akti, N. N.; Boeluekdemir, M. H.; Tel, E.

    2010-01-01

    In this study the nuclear energy level density based on nuclear collective excitation mechanism has been identified in terms of the low-lying collective level bands at near the neutron binding energy. Nuclear level density parameters of some light deformed medical radionuclides used widely in medical applications have been calculated by using different collective excitation modes of observed nuclear spectra. The calculated parameters have been used successfully in estimation of the neutron-capture cross section basic data for the production of new medical radionuclides. The investigated radionuclides have been considered in the region of mass number 40< A< 100. The method used in the present work assumes equidistance spacing of the collective coupled state bands of the interest radionuclides. The present calculated results have been compared with the compiled values from the literatures for s-wave neutron resonance data.

  6. A Parameter Study of Large Fast Reactor Nuclear Explosion Accidents

    Energy Technology Data Exchange (ETDEWEB)

    Wiesel, J R

    1969-02-15

    An IBM-code EEM (Explosive Excursion Model) has been developed for calculating the energy releases associated with the explosive disassembly of a large fast reactor following a superprompt critical condition. The assumed failure chain of events and the possible core collapse following a fuel meltdown give the input data and initial conditions, the most important of which is the reactivity insertion rate at the moment of the explosive core disassembly. The dependence of the energy releases on the reactivity insertion rate, the Doppler reactivity feedback, the power form factor and the core size have been studied. The model enables a quick estimation of conservative values of the destructive mechanical energy releases following a nuclear explosion and gives suggestions as to how to reduce or even avoid such excursions.

  7. A Parameter Study of Large Fast Reactor Nuclear Explosion Accidents

    International Nuclear Information System (INIS)

    Wiesel, J.R.

    1969-02-01

    An IBM-code EEM (Explosive Excursion Model) has been developed for calculating the energy releases associated with the explosive disassembly of a large fast reactor following a superprompt critical condition. The assumed failure chain of events and the possible core collapse following a fuel meltdown give the input data and initial conditions, the most important of which is the reactivity insertion rate at the moment of the explosive core disassembly. The dependence of the energy releases on the reactivity insertion rate, the Doppler reactivity feedback, the power form factor and the core size have been studied. The model enables a quick estimation of conservative values of the destructive mechanical energy releases following a nuclear explosion and gives suggestions as to how to reduce or even avoid such excursions

  8. Nuclear data project evaluation activity report. October 1998 - October 2000

    International Nuclear Information System (INIS)

    Akovali, Y.; Blackmon, J.; Radford, D.; Smith, M.

    2001-01-01

    This report summarizes the activities of the ORNL Nuclear Data Project since the IAEA Advisory Group meeting in December 1998. The group's future plans are also included. The ORNL Nuclear Data Project's responsibility includes the compilation/evaluation of astrophysics data, as well as the evaluation and compilation of nuclear structure data. The Nuclear Data Project, therefore, is composed of two groups. The Nuclear Data Project staff through September 2000 is listed below. Accomplishments for the period of October 1998 through September 2000 of the nuclear structure data group and the nuclear astrophysics group are submitted in this Nuclear Data Project report

  9. Nuclear data project evaluation activity report. October 1998 - October 2000

    Energy Technology Data Exchange (ETDEWEB)

    Akovali, Y; Blackmon, J; Radford, D; Smith, M [Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    2001-02-01

    This report summarizes the activities of the ORNL Nuclear Data Project since the IAEA Advisory Group meeting in December 1998. The group's future plans are also included. The ORNL Nuclear Data Project's responsibility includes the compilation/evaluation of astrophysics data, as well as the evaluation and compilation of nuclear structure data. The Nuclear Data Project, therefore, is composed of two groups. The Nuclear Data Project staff through September 2000 is listed below. Accomplishments for the period of October 1998 through September 2000 of the nuclear structure data group and the nuclear astrophysics group are submitted in this Nuclear Data Project report.

  10. Evaluated nuclear-data file for niobium

    International Nuclear Information System (INIS)

    Smith, A.B.; Smith, D.L.; Howerton, R.J.

    1985-03-01

    A comprehensive evaluated nuclear-data file for elemental niobium is provided in the ENDF/B format. This file, extending over the energy range 10 -11 -20 MeV, is suitable for comprehensive neutronic calculations, particulary those dealing with fusion-energy systems. It also provides dosimetry information. Attention is given to the internal consistancy of the file, energy balance, and the quantitative specification of uncertainties. Comparisons are made with experimental data and previous evaluated files. The results of integral tests are described and remaining outstanding problem areas are cited. 107 refs

  11. Evaluating decommissioning costs for nuclear power plants

    International Nuclear Information System (INIS)

    MacDonald, R.R.

    1980-01-01

    An overview is presented of the economic aspects of decommissioning of large nuclear power plants in an attempt to put the subject in proper perspective. This is accomplished by first surveying the work that has been done to date in evaluating the requirements for decommissioning. A review is presented of the current concepts of decommissioning and a discussion of a few of the uncertainties involved. This study identifies the key factors to be considered in the econmic evaluation of decommissioning alternatives and highlights areas in which further study appears to be desirable. 12 refs

  12. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    Baumann, B.L.

    1983-01-01

    The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

  13. DEVELOPING AND QUANTIFYING PARAMETERS FOR CLOSURE WELDING OVERPACKS CONTAINING RESEARCH REACTOR SPENT NUCLEAR FUEL AT HANFORD

    International Nuclear Information System (INIS)

    CANNELL GR

    2007-01-01

    Fluor engineers developed a Gas Tungsten Arc Welding (GTAW) technique and parameters, demonstrated requisite weld quality and successfully closure-welded packaged spent nuclear fuel (SNF) overpacks at the Hanford Site. This paper reviews weld development and qualification activities associated with the overpack closure-welding and provides a summary of the production campaign. The primary requirement of the closure weld is to provide leaktight confinement of the packaged material against release to the environment during interim storage (40-year design term). Required weld quality, in this case, was established through up-front development and qualification, and then verification of parameter compliance during production welding. This approach was implemented to allow for a simpler overpack design and more efficient production operations than possible with approaches using routine post-weld testing and nondestructive examination (NDE). . A series of welding trials were conducted to establish the desired welding technique and parameters. Qualification of the process included statistical evaluation and American Society of Mechanical Engineers (ASME) Section IX testing. In addition, pull testing with a weighted mockup, and thermal calculation/physical testing to identify the maximum temperature the packaged contents would be subject to during welding, was performed. Thirteen overpacks were successfully packaged and placed into interim storage. The closure-welding development activities (including pull testing and thermal analysis) provided the needed confidence that the packaged SNF overpacks could be safely handled and placed into interim storage, and remain leaktight for the duration of the storage term

  14. Evaluation method of nuclear nonproliferation credibility

    International Nuclear Information System (INIS)

    Kwon, Eun-ha; Ko, Won Il

    2009-01-01

    This paper presents an integrated multicriteria analysis method for the quantitative evaluation of a state's nuclear nonproliferation credibility level. Underscoring the implications of policy on the sources of political demand for nuclear weapons rather than focusing on efforts to restrict the supply of specific weapons technology from the 'haves' to the 'have-nots', the proposed methodology considers the political, social, and cultural dimensions of nuclear proliferation. This methodology comprises three steps: (1) identifying the factors that influence credibility formation and employing them to construct a criteria tree that will illustrate the relationships among these factors; (2) defining the weight coefficients of each criterion through pairwise comparisons of the Analytical Hierarchy Process (AHP); and (3) assigning numerical scores to a state under each criterion and combining them with the weight coefficients in order to provide an overall assessment of the state. The functionality of this methodology is examined by assessing the current level of nuclear nonproliferation credibility of four countries: Japan, North Korea, South Korea, and Switzerland.

  15. Large model-space calculation of the nuclear level density parameter

    International Nuclear Information System (INIS)

    Agrawal, B.K.; Samaddar, S.K.; De, J.N.; Shlomo, S.

    1998-01-01

    Recently, several attempts have been made to obtain nuclear level density (ρ) and level density parameter (α) within the microscopic approaches based on path integral representation of the partition function. The results for the inverse level density parameter K es and the level density as a function of excitation energy are presented

  16. Evaluated nuclear data file of Th-232

    International Nuclear Information System (INIS)

    Meadows, J.; Poenitz, W.; Smith, A.; Smith, D.; Whalen, J.; Howerton, R.

    1977-09-01

    An evaluated nuclear data file for thorium is described. The file extends over the energy range 0.049 (i.e., the inelastic-scattering threshold) to 20.0 MeV and is formulated within the framework of the ENDF system. The input data base, the evaluation procedures and judgments, and ancillary experiments carried out in conjunction with the evaluation are outlined. The file includes: neutron total cross sections, neutron scattering processes, neutron radiative capture cross sections, fission cross sections, (n;2n) and (n;3n) processes, fission properties (e.g., nu-bar and delayed neutron emission) and photon production processes. Regions of uncertainty are pointed out particularly where new measured results would be of value. The file is extended to thermal energies using previously reported resonance evaluations thereby providing a complete file for neutronic calculations. Integral data tests indicated that the file was suitable for neutronic calculations in the MeV range

  17. Chemistry technician performance evaluation program Palo Verde Nuclear Generating Station

    International Nuclear Information System (INIS)

    Shawver, J.M.

    1992-01-01

    The Arizona Nuclear Power Project (ANPP), a three-reactor site located 50 miles west of Phoenix, Arizona, has developed and implemented a program for evaluating individual chemistry technician analytical performance on a routine basis. About 45 chemistry technicians are employed at the site, 15 at each operating unit. The technicians routinely perform trace level analyses for impurities of concern to PWRs. Each month a set of blind samples is provided by an outside vendor. The blind samples contain 16 parameters which are matrixed to approximate the PWR's primary and secondary cycles. Nine technicians receive the samples, three from each operating unit, and perform the required analyses. Acceptance criteria for successful performance on the blind parameters is based on the values found in the Institute of Nuclear Power Operations (INPO) Document 83-016, Revision 2, August 1989, Chemistry Quality Control Program. The goal of the program is to have each technician demonstrate acceptable performance on each of 16 analytical parameters. On completion of each monthly set, a summary report of all of the analytical results for the sample set is prepared. From the summary report, analytical bias can be detected, technician performance is documented, and overall laboratory performance can be evaluated. The program has been very successful at satisfying the INPO requirement that the analytical performance of each individual technician should be checked on at least a six-month frequency for all important parameters measured. This paper describes the program as implemented at the Palo Verde Nuclear Generating Station and provides a summary report and trend and bias graphs for illustrative purposes

  18. Evaluation of trapping parameters of annealed natural quartz

    International Nuclear Information System (INIS)

    Zhou, Rui; Wei, Ming-Jian; Song, Bo; Zhang, Yan; Zhao, Qiu-Yue; Pan, Bao-Lin; Li, Teng-Fei

    2016-01-01

    The thermoluminescence (TL) trapping parameters of annealed quartz have been investigated. The apparent TL peaks observed at temperatures of 133 °C, 211 °C, 266 °C and 405 °C, respectively, were named Peak I, Peak II, Peak III and Peak IV. The T_m − T_s_t_o_p method is applied to investigate the number of peaks and their positions, and to obtain the trap distributions in the quartz. Peak shape (PS), Hoogenstraaten method (Various Heating Rates Method, VHR), and Computerized Glow Curve Deconvolution (CGCD) are used to evaluate the trapping parameters of the annealed quartz. The glow curve can be considered as a superposition of at least nine overlapping peaks. These peaks show up at 133 °C, 211 °C, 266 °C, 308 °C, 333 °C, 384 °C, 441 °C, 466 °C and 484 °C. The PS method can be only used in evaluating the parameters for Peaks I. The VHR method can be used in evaluating the trapping parameters for the first three peaks. CGCD method is complementary to obtaining parameters for the sub-peaks, and the thermal quenching correction with the Urbach’s method is necessary. The Urbach’s coefficient for the quartz is 30.03 kT_m.

  19. Evaluation of trapping parameters of annealed natural quartz

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, Rui [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China); Shisanling Seismic Station, Institute of Earthquake Science, CEA, 102200 Beijing (China); Wei, Ming-Jian, E-mail: weimj@cnu.edu.cn [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China); Song, Bo [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China); Beijing Jing Yuan School, 100040 Beijing (China); Zhang, Yan [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China); School of TaiPingqiao, Nan Lu of West Railway Station, 100073 Beijing (China); Zhao, Qiu-Yue [Key Laboratory of Tourism and Resources Environment in Universities of Shandong, Taishan University, 271000 Tai’an (China); Pan, Bao-Lin; Li, Teng-Fei [College of Resources, Environment & Tourism, Capital Normal University, 100048 Beijing (China)

    2016-05-15

    The thermoluminescence (TL) trapping parameters of annealed quartz have been investigated. The apparent TL peaks observed at temperatures of 133 °C, 211 °C, 266 °C and 405 °C, respectively, were named Peak I, Peak II, Peak III and Peak IV. The T{sub m} − T{sub stop} method is applied to investigate the number of peaks and their positions, and to obtain the trap distributions in the quartz. Peak shape (PS), Hoogenstraaten method (Various Heating Rates Method, VHR), and Computerized Glow Curve Deconvolution (CGCD) are used to evaluate the trapping parameters of the annealed quartz. The glow curve can be considered as a superposition of at least nine overlapping peaks. These peaks show up at 133 °C, 211 °C, 266 °C, 308 °C, 333 °C, 384 °C, 441 °C, 466 °C and 484 °C. The PS method can be only used in evaluating the parameters for Peaks I. The VHR method can be used in evaluating the trapping parameters for the first three peaks. CGCD method is complementary to obtaining parameters for the sub-peaks, and the thermal quenching correction with the Urbach’s method is necessary. The Urbach’s coefficient for the quartz is 30.03 kT{sub m}.

  20. Reduction of the chiral order parameter by a nuclear medium

    International Nuclear Information System (INIS)

    Kienle, P.; Yamazaki, Toshimizu

    2001-01-01

    We propose a model independent procedure to deduce from the 1s-binding energy of heavy, neutron rich pionic atoms, the isovector scattering length b 1 of the pion nucleus interaction. It is related to the pion decay constant f π , the order parameter of spontaneous chiral symmetry breaking and thus to the value of the chiral quark condensate. Based on the results with pionic 205 Pb, we find with the assertion that only the isovector part of the pion-nucleus interaction be modified by a QCD effect, a reduction of the quark condensate by 30% in a 205 Pb nucleus. Forthcoming experiments to measure pionic 1s-binding energies in Sn-isotopes, including isotope shifts, will yield decisive information on the quark condensate without assertion. (orig.)

  1. Regression analysis of radiological parameters in nuclear power plants

    International Nuclear Information System (INIS)

    Bhargava, Pradeep; Verma, R.K.; Joshi, M.L.

    2003-01-01

    Indian Pressurized Heavy Water Reactors (PHWRs) have now attained maturity in their operations. Indian PHWR operation started in the year 1972. At present there are 12 operating PHWRs collectively producing nearly 2400 MWe. Sufficient radiological data are available for analysis to draw inferences which may be utilised for better understanding of radiological parameters influencing the collective internal dose. Tritium is the main contributor to the occupational internal dose originating in PHWRs. An attempt has been made to establish the relationship between radiological parameters, which may be useful to draw inferences about the internal dose. Regression analysis have been done to find out the relationship, if it exist, among the following variables: A. Specific tritium activity of heavy water (Moderator and PHT) and tritium concentration in air at various work locations. B. Internal collective occupational dose and tritium release to environment through air route. C. Specific tritium activity of heavy water (Moderator and PHT) and collective internal occupational dose. For this purpose multivariate regression analysis has been carried out. D. Tritium concentration in air at various work location and tritium release to environment through air route. For this purpose multivariate regression analysis has been carried out. This analysis reveals that collective internal dose has got very good correlation with the tritium activity release to the environment through air route. Whereas no correlation has been found between specific tritium activity in the heavy water systems and collective internal occupational dose. The good correlation has been found in case D and F test reveals that it is not by chance. (author)

  2. Transfer parameters of fission and activation products present in effluents of nuclear power reactors

    International Nuclear Information System (INIS)

    Cancio, D.; Menossi, C.A.; Ciallella, N.R.

    1978-01-01

    The paper presents results of research carried out in Argentina on transfer parameters of fission and activation products which may be present in the effluents of nuclear power reactors. For some nuclides, as Sr-90, Co-137 and I-131, the parameters were obtained by studies of the fallout, from measurements of integrated levels in the environment and in the food chains. Other values are concentration factors derived from laboratory and field experiments. They refer to fish, molluscs, crustaces and fresh water plants, for several fission and activation nuclides. Transfer parameters obtained have been of significant importance for environmental assessments, relating to nuclear installations in Argentina. (author)

  3. Nuclear matter properties using different sets of parameters in the Gogny interaction

    International Nuclear Information System (INIS)

    Ramadan, Kh.A.; Mansour, H.M.M.

    2002-01-01

    In the present work we use the finite range density dependent effective Gogny interaction to study the equation of state of polarized nuclear matter. Six sets of the interaction parameters are used and a comparison is made with the calculations of Friedman and Pandharipande using a realistic interaction. One of the parameter sets (D1) gives similar results for the properties of polarized nuclear matter while the other parameter sets (D1S, D250, D260, D280 and D300) yield results which are reasonably comparable with the realistic interaction calculation of Friedman and Pandharipande. (author)

  4. New evaluation of 238U neutron resonance parameters

    International Nuclear Information System (INIS)

    Derrien, Herve; Leal, Luiz C.; Larson, Nancy M.

    2003-01-01

    The neutron resonance parameters of 238 U were obtained in the energy range 1 keV to 20 keV from a SAMMY Reich-Moore analysis of high resolution transmission measurements performed at ORELA. In the energy range 1 keV to 10 keV, the analysis used as prior values the ENDF/B-VI resonance parameters. The analysis in the energy range 10 keV to 20 keV resulted in the creation of a set of resonance parameters for the representation of the cross section in this energy range. The results are compared to the ENDF/B-VI evaluation. Some statistical properties of the new resonance parameters are examined. (author)

  5. Compilations and evaluations of nuclear structure and decay data

    International Nuclear Information System (INIS)

    Lorenz, A.

    1977-03-01

    This is the second issue of a report series on published and to-be-published compilations and evaluations of nuclear structure and decay (NSD) data. This compilation of compilations and evaluations is designed to keep the nuclear scientific community informed of the availability of compiled or evaluated NSD data, and contains references to laboratory reports, journal articles and books containing selected compilations and evaluations. It excludes references to ''mass-chain'' evaluations normally published in the ''Nuclear Data Sheets'' and ''Nuclear Physics''. The material contained in this compilation is sorted according to eight subject categories: general compilations; basic isotopic properties; nuclear structure properties; nuclear decay processes; half-lives, energies and spectra; nuclear decay processes: gamma-rays; nuclear decay processes: fission products; nuclear decay processes: (others); atomic processes

  6. Evaluation of selected sewage sludge gasification technological parameters

    Science.gov (United States)

    Gałko, Grzegorz; Król, Danuta

    2018-02-01

    Evaluation of selected sewage sludge gasification technological parameters was shown in this paper. Degree of carbon conducted in combustible substance and syngas efficiency (technological readiness coefficient) in accordance with equations were calculated. Enthalpy of individual compounds formation and energy balance were calculated in accordance with rule of Hess.

  7. Evaluation of quality parameters of strawberry fruits in modified ...

    African Journals Online (AJOL)

    The objective of the present study is to evaluate the effect of modified atmosphere packaging (MAP) during storage on some quality parameters of strawberries. Strawberries (cv. Camarosa) were harvested when mature, forced air cooled and divided into two groups as fruits in MAP and control. After packaging, fruits were ...

  8. Parameter values for the long-term nuclear waste management food chain model LIMCAL

    International Nuclear Information System (INIS)

    Zach, Reto.

    1982-09-01

    Eighteen parameters of LIMCAL, a comprehensive food chain model for predicting ICRP 26 50-year committed effective dose equivalents to man due to long-term nuclear waste management are reviewed. The parameters are: soil bulk density, plowlayer depth, soil surface layer depth, resusupension factor, atmospheric dust load, deposition velocity, plant interception fraction, plant environmental half-time, translocation factor, time of above-ground exposure, plant yield, holdup time, animals' feed consumption rate, animals' water consumption rate, man's water consumption rate, food type calorie conversion factors, man's total caloric intake rate and food type calorie fractions. LIMCAL has both traditional and unique parameters. The former occur in most of the currently used assessment models for nuclear installations, whereas the latter do not. For each of the parameters of LIMCAL, a suitable generic value for long-term nuclear waste management was determined. Thus, the general literature and the values currently used or recommended by various agencies were reviewed

  9. Development of nuclear methods for determining fluid-dynamic parameters in fluid catalyst cracking reactors

    International Nuclear Information System (INIS)

    Santos, V.A. dos; Dantas, C.C.

    1986-01-01

    Flow parameters of circulating fluidized bed in a simulated Fluid Catalyst Cracking reactor were determined by means of nuclear methods. The parameters were: residence time, density, inventory, circulation rate and radial distribution, for the catalyst; residence time for the gaseous phase. The nuclear methods where the gamma attenuation and the radiotracer. Two tracer techniques were developed, one for tagging of the catalyst by the 59 Fe as intrinsic tracer and another for tagging of the gaseous phase by the CH 3 82 Br as tracer. A detailed description of each measuring technique for all the investigated parameters is included. To carry out the determination for some of parameters a combination of the two methods was also applied. The results and the nuclear data are given in a table. (Author) [pt

  10. Global evaluation of nuclear infrastructure utilization scenarios (GENIUS)

    International Nuclear Information System (INIS)

    unzik-Gougar, Mary Lou; Juchau, Christopher A.; Pasamehmetoglu, Kemal; Wilson, Paul P.H.; Oliver, Kyle M.; Turinsky, Paul J.; Abdel-Khalik, Hany S.; Hays, Ross; Stover, Tracy E.

    2007-01-01

    A new and unique fuel cycle systems code has been developed. Need for this analysis tool was established via methodical development of technical functions and requirements followed by an evaluation of existing fuel cycle codes. As demonstrated by analysis of GNEP-type scenarios, the GENIUS code discretely tracks nuclear material from beginning to end of the fuel cycle and among any number of independent regions. Users can define scenarios starting with any/all existing reactors and fuel cycle facilities or with an ideal futuristic arrangement. Development and preliminary application of GENIUS capabilities in uncertainty analysis/propagation and multi-parameter optimization have also been accomplished. (authors)

  11. Mean nuclear volume

    DEFF Research Database (Denmark)

    Mogensen, O.; Sørensen, Flemming Brandt; Bichel, P.

    1999-01-01

    We evaluated the following nine parameters with respect to their prognostic value in females with endometrial cancer: four stereologic parameters [mean nuclear volume (MNV), nuclear volume fraction, nuclear index and mitotic index], the immunohistochemical expression of cancer antigen (CA125...

  12. Blind Source Parameters for Performance Evaluation of Despeckling Filters

    Directory of Open Access Journals (Sweden)

    Nagashettappa Biradar

    2016-01-01

    Full Text Available The speckle noise is inherent to transthoracic echocardiographic images. A standard noise-free reference echocardiographic image does not exist. The evaluation of filters based on the traditional parameters such as peak signal-to-noise ratio, mean square error, and structural similarity index may not reflect the true filter performance on echocardiographic images. Therefore, the performance of despeckling can be evaluated using blind assessment metrics like the speckle suppression index, speckle suppression and mean preservation index (SMPI, and beta metric. The need for noise-free reference image is overcome using these three parameters. This paper presents a comprehensive analysis and evaluation of eleven types of despeckling filters for echocardiographic images in terms of blind and traditional performance parameters along with clinical validation. The noise is effectively suppressed using the logarithmic neighborhood shrinkage (NeighShrink embedded with Stein’s unbiased risk estimation (SURE. The SMPI is three times more effective compared to the wavelet based generalized likelihood estimation approach. The quantitative evaluation and clinical validation reveal that the filters such as the nonlocal mean, posterior sampling based Bayesian estimation, hybrid median, and probabilistic patch based filters are acceptable whereas median, anisotropic diffusion, fuzzy, and Ripplet nonlinear approximation filters have limited applications for echocardiographic images.

  13. Blind Source Parameters for Performance Evaluation of Despeckling Filters.

    Science.gov (United States)

    Biradar, Nagashettappa; Dewal, M L; Rohit, ManojKumar; Gowre, Sanjaykumar; Gundge, Yogesh

    2016-01-01

    The speckle noise is inherent to transthoracic echocardiographic images. A standard noise-free reference echocardiographic image does not exist. The evaluation of filters based on the traditional parameters such as peak signal-to-noise ratio, mean square error, and structural similarity index may not reflect the true filter performance on echocardiographic images. Therefore, the performance of despeckling can be evaluated using blind assessment metrics like the speckle suppression index, speckle suppression and mean preservation index (SMPI), and beta metric. The need for noise-free reference image is overcome using these three parameters. This paper presents a comprehensive analysis and evaluation of eleven types of despeckling filters for echocardiographic images in terms of blind and traditional performance parameters along with clinical validation. The noise is effectively suppressed using the logarithmic neighborhood shrinkage (NeighShrink) embedded with Stein's unbiased risk estimation (SURE). The SMPI is three times more effective compared to the wavelet based generalized likelihood estimation approach. The quantitative evaluation and clinical validation reveal that the filters such as the nonlocal mean, posterior sampling based Bayesian estimation, hybrid median, and probabilistic patch based filters are acceptable whereas median, anisotropic diffusion, fuzzy, and Ripplet nonlinear approximation filters have limited applications for echocardiographic images.

  14. Economic evaluation of bids for nuclear power plants. 1999 edition

    International Nuclear Information System (INIS)

    2000-01-01

    The introduction of a nuclear power plant (NPP) in a country is a major undertaking for all entities involved. The necessary planning work and co-ordination of the different fields of interest, from the point of view of governments, authorities, industries, universities and of the general public, must be done on a long term basis. This IAEA report may help support the work of the utility in the bidding process, especially in the economic bid evaluation. The different methods, aspects and parameters described should be regarded as a guide. The report's target criterion of lowest levelised discounted electricity generation costs (LDEGC) is a very useful and practical way of ranking bids. In view of the huge investment needed, the owner's country must be fully committed to a nuclear programme. A nuclear programme also requires a guarantee of long term financing, which implies the provision of local and foreign contributions. The necessary staff for all of the various areas of a nuclear programme must be recruited and trained. Within the planning phase, the bid invitation specification (BIS) has to be prepared and sent out in order to receive bids for the scope of supply and services desired by the owner. The evaluation of the bids received from the suppliers in response to the BIS is a huge and long-term task. The evaluation process should lead to the selection of the best bidder and at least to the final decision on the partners constructing the NPP. The responsibility for the entire bidding process lies with the plant owner. For technology transfer, two requirements need to be satisfied: the owner needs a well established and experienced engineering capability, and the supplier must be ready to transfer the agreed technology in such a way as to support the project goals. During the bid evaluation process, all aspects of the technical, financial and contractual approaches must be considered. Nowadays, political, socioeconomic and public acceptance aspects play a

  15. Seismic evaluation of existing nuclear power plants

    International Nuclear Information System (INIS)

    2003-01-01

    The IAEA nuclear safety standards publications address the site evaluation and the design of new nuclear power plants (NPPs), including seismic hazard assessment and safe seismic design, at the level of the Safety Requirements as well as at the level of dedicated Safety Guides. It rapidly became apparent that the existing nuclear safety standards documents were not adequate for handling specific issues in the seismic evaluation of existing NPPs, and that a dedicated document was necessary. This is the purpose of this Safety Report, which is written in the spirit of the nuclear safety standards and can be regarded as guidance for the interpretation of their intent. Worldwide experience shows that an assessment of the seismic capacity of an existing operating facility can be prompted for the following: (a) Evidence of a greater seismic hazard at the site than expected before, owing to new or additional data and/or to new methods; (b) Regulatory requirements, such as periodic safety reviews, to ensure that the plant has adequate margins for seismic loads; (c) Lack of anti-seismic design or poor anti-seismic design; (d) New technical finding such as vulnerability of some structures (masonry walls) or equipment (relays), other feedback and new experience from real earthquakes. Post-construction evaluation programmes evaluate the current capability of the plant to withstand the seismic concern and identify any necessary upgrades or changes in operating procedures. Seismic qualification is distinguished from seismic evaluation primarily in that seismic qualification is intended to be performed at the design stage of a plant, whereas seismic evaluation is intended to be applied after a plant has been constructed. Although some guidelines do exist for the evaluation of existing NPPs, these are not established at the level of a regulatory guide or its equivalent. Nevertheless, a number of existing NPPs throughout the world have been and are being subjected to review of their

  16. Volcanic Hazards in Site Evaluation for Nuclear Installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-10-15

    This publication provides comprehensive and updated guidance for site evaluation in relation to volcanic hazards. It includes recommendations on assessing the volcanic hazards at a nuclear installation site, in order to identify and characterize, in a comprehensive manner, all potentially hazardous phenomena that may be associated with future volcanic events. It describes how some of these volcanic phenomena may affect the acceptability of the selected site, resulting in exclusion of a site or determining the corresponding design basis parameters for the installation. This Safety Guide is applicable to both existing and new sites, and a graded approach is recommended to cater for all types of nuclear installations. Contents: 1. Introduction; 2. Overview of volcanic hazard assessment; 3. General recommendations; 4. Necessary information and investigations (database); 5. Screening of volcanic hazards; 6. Site specific volcanic hazard assessment; 7. Nuclear installations other than nuclear power plants; 8. Monitoring and preparation for response; 9. Management system for volcanic hazard assessment; Annex I: Volcanic hazard scenarios; Annex II: Worldwide sources of information.

  17. The application of nuclear geophysics method to evaluate the geological environment of nuclear waste repository

    International Nuclear Information System (INIS)

    Fang, Fang; Xiaoqin, Wang; Kuanliang, Li; Xinsheng, Hou; Jingliang, Zhu; Binxin, Hu

    2002-01-01

    'Cleanly land should be given back ground.' This is a task while nuclear engineering have to be retired. We applied the nuclear geophysics methods and combined with geology, hydrology, geochemistry, and other methods, to evaluate the environment of nuclear waste repository. It is the important work to renovate environment and prepare technology before ex-service of the nuclear engineering

  18. Nondestructive evaluation of nuclear-grade graphite

    Science.gov (United States)

    Kunerth, D. C.; McJunkin, T. R.

    2012-05-01

    The material of choice for the core of the high-temperature gas-cooled reactors being developed by the U.S. Department of Energy's Next Generation Nuclear Plant Program is graphite. Graphite is a composite material whose properties are highly dependent on the base material and manufacturing methods. In addition to the material variations intrinsic to the manufacturing process, graphite will also undergo changes in material properties resulting from radiation damage and possible oxidation within the reactor. Idaho National Laboratory is presently evaluating the viability of conventional nondestructive evaluation techniques to characterize the material variations inherent to manufacturing and in-service degradation. Approaches of interest include x-ray radiography, eddy currents, and ultrasonics.

  19. Performance Evaluation and Parameter Identification on DROID III

    Science.gov (United States)

    Plumb, Julianna J.

    2011-01-01

    The DROID III project consisted of two main parts. The former, performance evaluation, focused on the performance characteristics of the aircraft such as lift to drag ratio, thrust required for level flight, and rate of climb. The latter, parameter identification, focused on finding the aerodynamic coefficients for the aircraft using a system that creates a mathematical model to match the flight data of doublet maneuvers and the aircraft s response. Both portions of the project called for flight testing and that data is now available on account of this project. The conclusion of the project is that the performance evaluation data is well-within desired standards but could be improved with a thrust model, and that parameter identification is still in need of more data processing but seems to produce reasonable results thus far.

  20. Study on human physiological parameters for monitoring of mental works in the nuclear power plant

    International Nuclear Information System (INIS)

    Takano, Ken-ichi; Yoshino, Kenji; Ishii, Keiichiro; Nakasa, Hiroyasu; Shigeta, Sadayoshi.

    1982-01-01

    To prevent outbreaks of the wrong operation and judgement in the nuclear power plant, human conditions of body and mind should be taken into consideration particularly for the mental works such as inspection and monitoring. To estimate human conditions quantitatively by the measurement of human physiological parameters, this paper presents the following experimental results. (1) Physiological parameters are estimated from both sides of biological meanings and the applicability to field works. (2) Time variation of the parameters is investigated in mental simulation tests in order to select a good indicator of mental fatigue. (3) Correlation analysis between mental fatigue indexes and physiological parameters shows that the heart rate is a best indicator. (author)

  1. Obtainment of nuclear power plant dynamic parameters by adaptive mesh technique

    International Nuclear Information System (INIS)

    Carvalho Miranda, W. de.

    1979-01-01

    This thesis involves the problem in determination of the parameters of the Mathematical Model of a Nuclear Reactor, including non-linearity which is considered as a bi-linear system. Being a non-linear model, the determination of its parameters cannot be made with the classical techniques as in obtaining its experimental frequency response. In the present work, we examine the possibility of using a model with parameters that adapt according to a algorithm of Newton type minimization, showing that in the case of the single parameter determination, the method is successful. This work was done, using the CSMP (Continuous System Modelling Program) of IBM 1130 of IME. (author)

  2. Nuclear criticality safety evaluation of Spray Booth Operations in X-705, Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Sheaffer, M.K.; Keeton, S.C.

    1993-01-01

    This report evaluates nuclear criticality safety for Spray Booth Operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current procedures and related hardware/equipment is presented. Control parameters relevant to nuclear criticality safety are explained, and a consolidated listing of administrative controls and safety systems is developed. Based on compliance with DOE Orders and MMES practices, the overall operation is evaluated, and recommendations for enhanced safety are suggested

  3. Evaluation of nonaqueous processes for nuclear materials

    International Nuclear Information System (INIS)

    Musgrave, B.C.; Grens, J.Z.; Knighton, J.B.; Coops, M.S.

    1983-12-01

    A working group was assigned the task of evaluating the status of nonaqueous processes for nuclear materials and the prospects for successful deployment of these technologies in the future. In the initial evaluation, the study was narrowed to the pyrochemical/pyrometallurgical processes closely related to the processes used for purification of plutonium and its conversion to metal. The status of the chemistry and process hardware were reviewed and the development needs in both chemistry and process equipment technology were evaluated. Finally, the requirements were established for successful deployment of this technology. The status of the technology was evaluated along three lines: (1) first the current applications were examined for completeness, (2) an attempt was made to construct closed-cycle flow sheets for several proposed applications, (3) and finally the status of technical development and future development needs for general applications were reviewed. By using these three evaluations, three different perspectives were constructed that together present a clear picture of how complete the technical development of these processes are

  4. Analysis and Evaluation of Cooking Parameters for Sweet Bakery Products

    OpenAIRE

    Giuseppe Vignali; Andrea Volpi

    2013-01-01

    Cooking process is essential for the preparation of sweet bakery products, such as Panettone, a typical Italian seasonal dessert. This study is aimed at evaluating the features of the finished product leaving the oven chamber using the Design of Experiments technique. Four features of the product like “water activity”, “humidity”, “pH” and “sensorial judge” have been explained as functions of independent variables: recipe of the dough, affecting the dough strength and cooking process paramete...

  5. Use of Covariances in a Consistent Data Assimilation for Improvement of Basic Nuclear Parameters in Nuclear Reactor Applications: From Meters to Femtometers

    International Nuclear Information System (INIS)

    Herman, Mike; Hoblit, Sam; Gustavo, Nobre; Palumbo, Annalia; Pigni, M.T.; Palmiotti, G.; Hiruta, H.; Salvatores

    2013-01-01

    neutron energy spectrum that are adopted in the assimilation (adjustment). In fact, after such an adjustment is performed, neutronic designers are then tied to this energy group structure and neutron energy spectrum when carrying out further calculations. In reality, this can be quite a limiting factor in view of the complex spectral issues that are involved in most reactor physics. This work combines novel, but proven, methodologies for overcoming these limitations. In fact, this is the first attempt to build up a link between the wealth of precise integral experiments and a basic theory of nuclear reactions. Essential ingredients of such a procedure, denominated here as assimilation, are covariances for model parameters and sensitivity matrices. The latter provide direct link between reaction theory and integral experiments. The result is a consistent data assimilation performed directly on the basic nuclear physics parameters that are being used in a variety of nuclear reaction mechanisms. The resulting improvement in their performance will consequently reduce related uncertainties when employed in reactor calculations. By using integral reactor physics experiments (meter scale), information is propagated back to the nuclear physics level (femtometers) covering a range of more than 13 orders of magnitude. The assimilation procedure should result in more accurate and more reliable evaluated data files of universal validity rather than tailored to a particular application. In fact, after data assimilation is carried out, the basic nuclear data file can be processed by a dedicated code into any energy group structure that the reactor physicist deems to be useful. On the other hand, integral experiments used in the assimilation should provide additional, possibly quite strict, constraints on the parameters entering nuclear reaction modeling, as well as the reaction models themselves. This report describes three years of combined research by Brookhaven National Lab (BNL

  6. Evaluation of uncertainties of key neutron parameters of PWR-type reactors with slab fuel, application to neutronic conformity

    International Nuclear Information System (INIS)

    Bernard, D.

    2001-12-01

    The aim of this thesis was to evaluate uncertainties of key neutron parameters of slab reactors. Uncertainties sources have many origins, technologic origin for parameters of fabrication and physical origin for nuclear data. First, each contribution of uncertainties is calculated and finally, a factor of uncertainties is associated to key slab parameter like reactivity, isotherm reactivity coefficient, control rod efficiency, power form factor before irradiation and life-time. This factors of uncertainties were computed by Generalized Perturbations Theory in case of step 0 and by directs calculations in case of irradiation problems. One of neutronic conformity applications was about fabrication and nuclear data targets precision adjustments. Statistic (uncertainties) and deterministic (deviations) approaches were studied. Then, neutronics key slab parameters uncertainties were reduced and so nuclear performances were optimized. (author)

  7. Ship nuclear power plants: system approach designing and optimal parameter selection

    International Nuclear Information System (INIS)

    Dolgov, V.N.

    1995-01-01

    Dependence of basic indices of naval nuclear power installations on combination of thermotechnical parameters is considered. The necessity of new approach to designing naval nuclear power facilities, based on combined analysis of the above facilities and the ship, as a single complex system, is demonstrated. The conclusion is made that unjustified increase in the ship metal capacity, terms and costs of their production takes place in case of disregarding the role of mass and dimensions of nuclear power facilities and consequently their thermotechnical characteristics in formation of the ship displacement tonnage. 2 refs., 3 figs

  8. Design characteristics of safety parameter display system for nuclear power plants

    International Nuclear Information System (INIS)

    Zhang Yuangfang

    1992-02-01

    The design features of safety parameter display system (SPDS) developed by Tsinghua University is introduced. Some new features have been added into the system functions and they are: (1) hierarchical display structure; (2) human factor in the display format design; (3)automatic diagnosis of safety status of nuclear power plant; (4) extension of SPDS use scope; (5) flexible hardware structure. The new approaches in the design are: (1)adopting the international design standards; (2) selecting safety parameters strictly; (3) developing software under multitask operating system; (4) using a nuclear power plant simulator to verify the SPDS design

  9. Distribution and Parameter's Calculations of Television Cameras Inside a Nuclear Facility

    International Nuclear Information System (INIS)

    El-kafas, A.A.

    2009-01-01

    In this work, a distribution of television cameras and parameter's calculation inside and outside a nuclear facility is presented. Each of exterior and interior camera systems will be described and explained. The work shows the overall closed circuit television system. Fixed and moving cameras with various lens format and different angles of view are used. The calculations of width of images sensitive area and Lens focal length for the cameras will be introduced. The work shows the camera locations and distributions inside and outside the nuclear facility. The technical specifications and parameters for cameras selection are tabulated

  10. Principles and problems in neutron nuclear data evaluation

    International Nuclear Information System (INIS)

    Schmidt, J.J.

    1967-01-01

    The history of neutron nuclear data evaluation is briefly summarized. The physical problems involved in nuclear data evaluation, such as discrepancies and inconsistencies between different experimental data sets and gaps in experimental information, are discussed. The discrepancies in the capture cross-section data for molybdenum and iron are chosen to illustrate the great difficulties in systematizing and automatizing the evaluation process. The technical problems of data evaluation, such as computer storage and the establishment of nuclear data files, are not discussed. (author)

  11. Compilations and evaluations of nuclear structure and decay data

    International Nuclear Information System (INIS)

    Lorenz, A.

    1977-10-01

    This is the third issue of a report series on published and to-be-published compilations and evaluations of nuclear structure and decay (NSD) data. This compilation is published and distributed by the IAEA Nuclear Data Section approximately every six months. This compilation of compilations and evaluations is designed to keep the nuclear scientific community informed of the availability of compiled or evaluated NSD data, and contains references to laboratory reports, journal articles and books containing selected compilations and evaluations

  12. Compilations and evaluations of nuclear structure and decay data

    International Nuclear Information System (INIS)

    Lorenz, A.

    1978-10-01

    This is the fourth issue of a report series on published and to-be-published compilations and evaluations of nuclear structure and decay (NSD) data. This compilation is published and distributed by the IAEA Nuclear Data Section every year. The material contained in this compilation is sorted according to eight subject categories: General compilations; basic isotopic properties; nuclear structure properties; nuclear decay processes, half-lives, energies and spectra; nuclear decay processes, gamma-rays; nuclear decay processes, fission products; nuclear decay processes (others); atomic processes

  13. Latest 'evaluation of size of economy' for nuclear uses

    International Nuclear Information System (INIS)

    Saito, Shinzo; Kume, Tamikazu; Inoue, Tomio; Takahashi, Shoji

    2008-01-01

    Size of economy for nuclear uses in Japan was evaluated for FY 2005. Nuclear uses are classified into nuclear energy use and radiation utilizations. Nuclear energy use totaled 4.7 trillion yen with nuclear power. Economy size of nuclear power decreased due to disgraceful events and accidents, though 5.5 trillion yen around for FY 2000. Radiation utilizations totaled 4.1 trillion yen mainly with industrial uses (2.3 trillion yen) and nuclear medicine, diagnosis and radiotherapy (1.5 trillion yen). Combined total of uses amounted to 8.9 trillion yen and comparable with 9.5 trillion yen for FY 1997. (T. Tanaka)

  14. Nuclear parameters determination of the 127Te β - decay: a proposal for teaching nuclear physics

    International Nuclear Information System (INIS)

    Batista, Wagner Fonseca

    2011-01-01

    A study of the 127 Te β - decay was carried out by means of gamma spectroscopy measurements using high resolution HPGe detector, in the region from 30 keV to 1.0 MeV, aiming to get a better understanding of the 127 Te nuclear structure. The radioactive sources of 12 7Te were obtained from the 126 Te(n,γ) 1 '2 7 Te nuclear reaction produced in the IEA- R1 nuclear reactor at IPEN/CNEN-SP. Five gamma t ransitions previously attributed to this decay were confirmed with a better precision than previously. The half-life of 127 Te was also studied resulting in data with lower uncertainty. Using a set of data selected from gamma spectroscopy measurements was developed and applied a didactic proposal for high school students using the Excel software. (author)

  15. A systematic study of distribution characters of infiltration parameters in an experimental basin by nuclear methods

    International Nuclear Information System (INIS)

    Gu Weizu; Lu Jieju; Lu Mingjiang; Chen Tingyang

    1988-01-01

    A case study of spatial variability of Philip's infiltration parameters was carried out in a small experimental catchment with an area of 0.8 ha by nuclear monitoring methods. Relationships between sorptivity S, parameter A and the average initial soil water content within 0.5 m depth of soil profiles over the catchment have been plotted. A watershed infiltration parameter distribution curve is set up and fitted approximately by f/F=1-(1-S/S M ) n . The parameters of composite infiltration response related to whole catchment are suggested. The author has studied it on an experimental basin by combined method of nuclear technology and micro-geomorphic analysis. The results are satisfactory. (author). 6 refs, 11 figs, 2 tabs

  16. Development of graphic display program of reactor operating parameters for emergency exercise at nuclear power plants

    International Nuclear Information System (INIS)

    Okuda, Yasunori; Yoshida, Yoshitaka; Gotou, Kazuko

    2001-01-01

    A scenario of nuclear emergency exercise based on the result of accident progress analysis is expected to ensure effective training. Thereupon a new graphic display program for reactor operating parameters has been developed to present real-time of plant process values (parameters), released radioactivities from the plant, and dose rate data around the site calculated by using the accident analysis code MAAP4 and other codes. This system has a trend graph screen displaying reactor operating parameters, an environmental dose rate summary screen indicating dose rate distribution around the site on the map, and a plant parameters summary screen showing important plant parameters on a simplified plant system diagram. One screen can be switched to another any time. It also has a jump-function easily accessing any stage during the exercise scenario in accordance with progress of the exercise. As a result of the application of this system to a real nuclear emergency exercise, it has been verified that this system is quite useful for confirming the parameters when the nuclear emergency exercise starts and the licensee reports the plant conditions to related bodied. (author)

  17. Development of graphic display program of reactor operating parameters for emergency exercise at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Okuda, Yasunori; Yoshida, Yoshitaka [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Gotou, Kazuko [Kansai Electric Power Co., Inc., Osaka (Japan)

    2001-09-01

    A scenario of nuclear emergency exercise based on the result of accident progress analysis is expected to ensure effective training. Thereupon a new graphic display program for reactor operating parameters has been developed to present real-time of plant process values (parameters), released radioactivities from the plant, and dose rate data around the site calculated by using the accident analysis code MAAP4 and other codes. This system has a trend graph screen displaying reactor operating parameters, an environmental dose rate summary screen indicating dose rate distribution around the site on the map, and a plant parameters summary screen showing important plant parameters on a simplified plant system diagram. One screen can be switched to another any time. It also has a jump-function easily accessing any stage during the exercise scenario in accordance with progress of the exercise. As a result of the application of this system to a real nuclear emergency exercise, it has been verified that this system is quite useful for confirming the parameters when the nuclear emergency exercise starts and the licensee reports the plant conditions to related bodied. (author)

  18. Evaluation of Reliability Parameters in Micro-grid

    Directory of Open Access Journals (Sweden)

    H. Hasanzadeh Fard

    2015-06-01

    Full Text Available Evaluation of the reliability parameters in micro-grids based on renewable energy sources is one of the main problems that are investigated in this paper. Renewable energy sources such as solar and wind energy, battery as an energy storage system and fuel cell as a backup system are used to provide power to the electrical loads of the micro-grid. Loads in the micro-grid consist of interruptible and uninterruptible loads. In addition to the reliability parameters, Forced Outage Rate of each component and also uncertainty of wind power, PV power and demand are considered for micro-grid. In this paper, the problem is formulated as a nonlinear integer minimization problem which minimizes the sum of the total capital, operational, maintenance and replacement cost of DERs. This paper proposes PSO for solving this minimization problem.

  19. The evaluation of some thermodynamic parameters by RIA method

    International Nuclear Information System (INIS)

    Dorobantu, I. I.; Cucu Delia-Irina

    2001-01-01

    The present paper evaluates some of thermodynamic parameters by using RIA (radioimmunoassay) method. The RIA systems studied were: 1) antiprogesterone antibody-progesterone- 3 H; 2) antiprogesterone antibody-progesterone- 125 I. The antigen (progesterone) was labelled with 3 H, in the first case, and 125 I in the second one (progesterone- 125 I was progesterone-6-S-CH 2 -CO-histamine- 125 I). RIA reactions were developed at two temperatures: 277 K and 296 K. Samples of antiprogesterone antibodies and labelled progesterone were incubated with different amounts of unlabeled progesterone. The immune complex was precipitated after reaching the chemical equilibrium and its radioactivity measured at γ-counter. By the radioactive measurements, the affinity constants (K S ) were estimated. The values of the affinity constants were used to estimate the thermodynamic parameters of the systems, such as: enthalpy (ΔH), Gibbs energy (ΔG) and entropy (ΔS). (authors)

  20. Nuclear imaging evaluation of galactosylation of chitosan

    International Nuclear Information System (INIS)

    Jeong, Hwan Jeong; Kim, Eun Mi; Kim, Chang Guhn; Park, In Kyu; Cho, Chong Su; Bom, Hee Seung

    2004-01-01

    Chitosan has been studied as a non-viral gene delivery vector, drug delivery carrier, metal chelater, food additive, and radiopharmaceutical, among other things. Recently, galactose-graft chitosan was studied as a non-viral gene and drug delivery vector to target hepatocytes. The aim of this study was to investigate the usefulness of nuclear imaging for in vivo evaluation of targeting the hepatocyte by galactose grafting. Galactosyl methylated chitosan (GMC) was produced by methylation to lactobionic acid coupled chitosan Cytotoxicity of 99 mTc-GMC was determined by MTT assay. Rabbits were injected via their auricular vein with 99 mTc-GMC and 99 mTc-methylated chitosan (MC), the latter of which does not contain a galactose group, and images were acquired with a gamma camera equipped with a parallel hole collimator. The composition of the galactose group in galactosylated chitosan (GC), as well as the tri-, di-, or mono-methylation of GMC, was confirmed by NMR spectroscopy. The results of MTT assay indicated that 99 mTc-GMC was non-toxic. 99 mTc-GMC specifically accumulated in the liver within 10 minutes of injection and maintained high hepatic uptake. In contrast, 99 mTc-MC showed faint liver uptake. 99 mTc-GMC scintigraphy of rabbits showed that the galactose ligand principally targeted the liver while the chitosan functionalities led to excretion through the urinary system. Bioconjugation with a specific ligand endows some degree of targetability to an administered molecule or drug, as in the case of galactose for hepatocyte in vivo, and evaluating said targetability is a clear example of the great benefit proffered by nuclear imaging

  1. Measurement of the meteorological parameters in Almirante Alvaro Alberto nuclear power plant using captive balloon

    International Nuclear Information System (INIS)

    Silva Lobo, M.A. da; Lima e Silva Filho, P.P. de; Eschebach, B.M.

    1984-01-01

    A methodology to obtain the meteorological parameters in the vicinity of the Almirante Alvaro Alberto nuclear power plant is presented. The study of the atmospheric dispersion is done by the analysis of the results and it is a complement of the meteorological operation of Angra-1 and pre-operation of Angra-2 and 3 program. (M.C.K.) [pt

  2. Effects of pairing correlation on nuclear level density parameter and nucleon separation energy

    International Nuclear Information System (INIS)

    Rajesekaran, T.R.; Selvaraj, S.

    2002-01-01

    A systematic study of effects of pairing correlations on nuclear level density parameter 'a' and neutron separation energy S N is presented for 152 Gd using statistical theory of nuclei with deformation, collective and noncollective rotational degrees of freedom, shell effects, and pairing correlations

  3. Research on psychological evaluation method for nuclear power plant operators

    International Nuclear Information System (INIS)

    Fang Xiang; He Xuhong; Zhao Bingquan

    2007-01-01

    The qualitative and quantitative psychology evaluation methods to the nuclear power plant operators were analyzed and discussed in the paper. The comparison analysis to the scope and result of application was carried out between method of outline figure fitted and method of fuzzy synthetic evaluation. The research results can be referenced to the evaluation of nuclear power plant operators. (authors)

  4. Study of the nuclear-coulomb low-energy scattering parameters on the basis of the p-matrix approach

    International Nuclear Information System (INIS)

    Babenko, V.A.; Petrov, N.M.

    1993-01-01

    The P-matrix approach application to the description of two charged strongly interacting particles nuclear-Coulomb scattering parameters is considered. The nuclear-Coulomb scattering length and effective range explicit expressions in terms of the P-matrix parameters are found. The nuclear-Coulomb low-energy parameters expansions in powers of small parameter β ≡ R/a b , involving terms with big logarithms, are obtained. The nuclear-Coulomb scattering length and effective range for the square-well and the delta-shell short range potentials are found in an explicit form. (author). 21 refs

  5. INPRO Methodology to evaluate the Mexico nuclear energy system; Metodologia INPRO para evaluar el sistema de energia nuclear de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Cruz S, R. R.; Martin del C, C., E-mail: crzslns.ricardoruben@gmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2016-09-15

    The International Atomic Energy Agency has developed the so-called International Project on Fuel Cycles and Innovative Nuclear Reactors (INPRO), in order to make nuclear energy available to meet the energy needs of the 21 century, in a sustainable way. One of the tasks of the project is the evaluation of the nuclear systems, to check whether they meet the objectives of the project and whether they are sustainable. This paper explains the rationale and general characteristics of the project in the evaluation of nuclear energy systems based on the concept of sustainable development. It describes the methodology developed to carry out this evaluation, divided into seven areas, such as economic, environmental, security, etc., which together make up the sustainable development of energy through nuclear systems. The economic area is analyzed and the evaluation criteria and parameters established by INPRO are discussed, in order to evaluate the Mexican nuclear energy system using Nest (software developed within the same project) as a tool to support the economic evaluation of nuclear systems. Based on the energy strategy proposed by the Energy Secretary of the Mexican Government which seeks to reduce the greenhouse gas emissions from the national electricity generation park, two types of reactor of currently available technology (A BWR and AP1000), were compared and these in turn with other alternative energy generation technologies, such as combined cycle, geothermal and wind plants. Also, the results of the application of the INPRO methodology are presented. Finally, the recommendations on actions that could lead the Mexican nuclear energy system towards sustainable development and conclusions on the application of the methodology to the Mexican case are mentioned. (Author)

  6. International co-operation in nuclear data evaluation

    International Nuclear Information System (INIS)

    Nordborg, C.

    2003-01-01

    The NEA Working Party on International Nuclear Data Evaluation Co-operation serves as a forum for the exchange of information on required improvements to evaluated nuclear data libraries used in all nuclear application areas. The main objective is to identify the major discrepancies in existing evaluated data libraries and to resolve these discrepancies in specifically established expert groups. The long-term goal is to have converging evaluated data libraries. This co-operative effort is very successful. It has resolved a number of outstanding nuclear data problems and has issued 15 reports in support of the studies undertaken jointly. (author)

  7. A plan for safety evaluation of tsunamis at the Uljin nuclear power plant site

    International Nuclear Information System (INIS)

    Lee, H. K.; Lee, D. S.

    1999-01-01

    The sites of many nuclear and thermal power plants are located along the coast line to obtain necessary cooling water. Therefore, they are vulnerable to coastal disasters like tsunamis. The safety evaluation on tsunamis of the site of Uljin nuclear power plants was performed with the maximum potential earthquake magnitude and related fault parameters in 1986. But according to the results of recent research, the possibility was suggested that the earthquake which has bigger magnitude than was expected is likely to happen in the seismic gaps near Akita, Japan. Therefore, a plan for safety evaluation of tsunamis at the Uljin nuclear power plants was laid out

  8. Effects of different SSI parameters on the floor response spectra of a nuclear reactor building

    International Nuclear Information System (INIS)

    Kabir, A.F.; Bolourchi, S.; Maryak, M.E.

    1991-01-01

    The effects of several critical soil-structure interaction (SSI) parameters on the floor response spectra (FRS) of a typical nuclear reactor building have been examined. These parameters are computation of soil impedance functions using different approaches, scattering effects (reductions in ground motion due to embedment and rigidity of building foundation) and strain dependency of soil dynamic properties. This paper reports that the significant conclusions of the study, which are applicable to a deeply embedded very rigid nuclear reactor building, are as follows: FRS generated without considering scattering effects are highly conservative; differences between FRS, generated considering strain-dependency of soil dynamic properties, and those generated suing low-strain values, are not significant; and the lumped-parameter approach of SSI calculations, which only uses a single value of soil shear modulus in impedance calculations, may not be able to properly compute the soil impedances for a soil deposit with irregularly varying properties with depth

  9. Progress on reference input parameter library for nuclear model calculations of nuclear data (III)

    International Nuclear Information System (INIS)

    Su Zongdi; Liu Jianfeng; Huang Zhongfu

    1997-01-01

    A new set of the average neutron resonance spacings D 0 and neutron strength functions S 0 for 309 nuclei were reestimated on the basis of the resolved resonance parameters reevaluated from BNL-325, ENDF/B-6, JEF-2, and JENDL-3, and the cumulative number N 0 of low low lying levels for 344 nuclei were also reevaluated by means of histograms. Three sets of level density parameters for the Gilbert-Cameron (GC) formula, back-shifted Fermi gas model(BS) and generated superfluid model (GSM) have been reesitmated by fitting the D 0 and N 0 values of CENPL.LRD-2

  10. Feasibility Study on Nuclear Propulsion Ship according to Economic Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Gil, Youngmi; Yoo, Seongjin; Oh, June; Byun, Yoonchul; Woo, Ilguk [Daewoo Shipbuilding and Marine Engineering Co., Ltd, Seoul (Korea, Republic of); Kim, Jiho; Choi, Suhn [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The use of nuclear ships has been extending to the icebreaker, the deep-water exploration ship, and the floating nuclear power plant. Prior to developing the new ship, the relevant regulations need to be considered. In this study, we reviewed the nuclear ship-related regulations. In addition, economic value is one of the most important factors which should be considered in the pre-design phase. To evaluate the economics of the nuclear ship, we calculated Capital Expenditure (abbreviated as CAPEX) and Operation Expenditure (abbreviated as OPEX) for various types of ships. We reviewed the nuclear ship-related regulations and evaluated the economics of the nuclear ship compared to the diesel ship. The calculation result shows that economic feasibility of the nuclear ship depends on the oil price as well as the cost of the nuclear reactor.

  11. Operational safety performance and economical efficiency evaluation for nuclear power plants

    International Nuclear Information System (INIS)

    Liu Yachun; Zou Shuliang

    2012-01-01

    The economical efficiency of nuclear power includes a series of environmental parameters, for example, cleanliness. Nuclear security is the precondition and guarantee for its economy, and both are the direct embodiment of the social benefits of nuclear power. Through analyzing the supervision and management system on the effective operation of nuclear power plants, which has been put forward by the International Atomic Energy Agency (IAEA), the World Association of Nuclear Operators (WANO), the U.S. Nuclear Regulatory Commission (NRC), and other organizations, a set of indexs on the safety performance and economical efficiency of nuclear power are explored and established; Based on data envelopment analysis, a DEA approach is employed to evaluate the efficiency of the operation performance of several nuclear power plants, Some primary conclusion are achieved on the basis of analyzing the threshold parameter's sensitivity and relativity which affected operational performance. To address the conflicts between certain security and economical indicators, a multi-objective programming model is established, where top priority is given to nuclear safety, and the investment behavior of nuclear power plant is thereby optimized. (authors)

  12. Evaluation of some infiltration models and hydraulic parameters

    International Nuclear Information System (INIS)

    Haghighi, F.; Gorji, M.; Shorafa, M.; Sarmadian, F.; Mohammadi, M. H.

    2010-01-01

    The evaluation of infiltration characteristics and some parameters of infiltration models such as sorptivity and final steady infiltration rate in soils are important in agriculture. The aim of this study was to evaluate some of the most common models used to estimate final soil infiltration rate. The equality of final infiltration rate with saturated hydraulic conductivity (Ks) was also tested. Moreover, values of the estimated sorptivity from the Philips model were compared to estimates by selected pedotransfer functions (PTFs). The infiltration experiments used the doublering method on soils with two different land uses in the Taleghan watershed of Tehran province, Iran, from September to October, 2007. The infiltration models of Kostiakov-Lewis, Philip two-term and Horton were fitted to observed infiltration data. Some parameters of the models and the coefficient of determination goodness of fit were estimated using MATLAB software. The results showed that, based on comparing measured and model-estimated infiltration rate using root mean squared error (RMSE), Hortons model gave the best prediction of final infiltration rate in the experimental area. Laboratory measured Ks values gave significant differences and higher values than estimated final infiltration rates from the selected models. The estimated final infiltration rate was not equal to laboratory measured Ks values in the study area. Moreover, the estimated sorptivity factor by Philips model was significantly different to those estimated by selected PTFs. It is suggested that the applicability of PTFs is limited to specific, similar conditions. (Author) 37 refs.

  13. Multimethods approach to safety-parameter-display evaluation

    International Nuclear Information System (INIS)

    Banks, W.W.; Blackman, H.S.; Gertman, D.I.; Petersen, R.J.

    1982-01-01

    The Human Factors Engineering Office of EG and G Idaho performed this NRC-funded study to assist the NRC in objectively assessing licensee-developed safety parameter display (SPD) formats and designs. The purpose of this study was to quantitatively measure the degree to which a tachistoscopic method of display evaluation would correlate with the results of a multidimensional rating approach to display evaluation. Results of the following three experiments will be presented; (a) tachistoscopic, (b) multidimensional rating scale, and (c) the combined results of a and b. The test material for all experiments consisted of three multivariate data display formats all under development as SPDs for reactor control rooms presenting safety parameter display data at the loss-of-fluid test (LOFT) facility. The three display formats studied were stars, deviation bar graphs, and meters. Eighteen adult volunteers were used as subjects. All were currently qualified reactor operators from the LOFT reactor plant, with a mean of 9.4 years reactor operating experience

  14. Determination of Nuclear Track Parameters for LR-115 Detector by Using of MATLAB Software Technique

    International Nuclear Information System (INIS)

    AL-Jomaily, F.M.; AL-joburi, H.A.; Mheemeed, A.K.

    2013-01-01

    The nuclear track detector parameters, such as nuclear track diameter D(μm), number of track N T and area of track A T were determined by using MATLAB software technique for IR-115 detector irradiated by alpha particle from 241 Am source under 1.5, 2.5 and 3.5 MeV at etching time T B of 90, 120, 150 and 180 min.By using the image analysis of MATLAB software for nuclear track, the full width at half maximum FWHM and relative resolution R% were calculated for each energy of alpha particles.In this study, it was shown that increasing the alpha energy on the IR-115 detector leads to increased etching time T B and the dropping of R% to minimum value, and then reach a stable value before dropping at values 1.5, 2.5 MeV and unstable at 3.5 MeV. Imaging analysis by MATLAB technique which used in this study reflect good and accurate results for nuclear track detector parameters and we recommend using this technique for determination of these parameters

  15. Status of transactinium nuclear data in the evaluated nuclear structure data file

    International Nuclear Information System (INIS)

    Ewbank, W.B.

    1980-01-01

    The structure and organization of the Evaluated Nuclear Structure Data File (ENSDF) which serves as the source data base for the production of drawings and tables for the ''Nuclear Data Sheets'' journal is described. The updating and output features of ENSDF are described with emphasis on nuclear structure and decay data of the transactinium isotopes. (author)

  16. Parameters of Instrumental Swallowing Evaluations: Describing a Diagnostic Dilemma.

    Science.gov (United States)

    Pisegna, Jessica M; Langmore, Susan E

    2016-06-01

    The aim of this study was to compare selected parameters of two swallow evaluations: fiberoptic endoscopic evaluation of swallowing (FEES) and the modified barium swallow (MBS) study. This was a cross-sectional, descriptive study. Fifty-five clinicians were asked to watch video recordings of swallow evaluations of 2 patients that were done using fluoroscopy and endoscopy simultaneously. In a randomized order, clinicians viewed 4 edited videos from simultaneous evaluations: the FEES and MBS videos of patient 1 and 2 each taking one swallow of 5 mL applesauce. Clinicians filled out a questionnaire that asked (1) which anatomical sites they could visualize on each video, (2) where they saw pharyngeal residue after a swallow, (3) their overall clinical impression of the pharyngeal residue, and (4) their opinions of the evaluation styles. Clinicians reported a significant difference in the visualization of anatomical sites, 11 of the 15 sites were reported as better-visualized on the FEES than on the MBS video (p < 0.05). Clinicians also rated residue to be present in more locations on the FEES than on the MBS. Clinicians' overall impressions of the severity of residue on the same exact swallow were significantly different depending on the evaluation type (FEES vs. MBS for patient 1 χ(2) = 20.05, p < 0.0001; patient 2 χ(2) = 7.52, p = 0.006), with FEES videos rated more severely. FEES advantages were: more visualization of pharyngeal and laryngeal swallowing anatomy and residue. However, as a result, clinicians provided more severe impressions of residue amount on FEES. On one hand, this suggests that FEES is a more sensitive tool than MBS studies, but on the other hand, clinicians might provide more severe interpretations on FEES.

  17. Multi-criteria Evaluation of Nuclear Option

    International Nuclear Information System (INIS)

    Feretic, D.; Tomsic, Z.; Jaksic, D.

    2002-01-01

    When evaluating power system expansion scenarios there is a need to take into consideration a range of measurable and non-measurable impacts. Measurable impacts are fixed and variable production costs and, recently, external costs. Non-measurable impacts include public attitude to certain energy technology and investor's risk in achieving the expected profit (regulatory and political risk). Public attitude has a large and sometimes essential impact on decision-making. It is mostly associated with the expected environmental impact of a potential power plant and can be divided in rational and non-rational part. Rational part, which is in proportion with scientifically approved environmental impact of energy options (inversely proportional to external costs) is relatively small, while the other, non-rational category which is not proportional with the actual environmental impact (especially in the case of nuclear power), is much larger. Investor's risk in achieving the expected profit is mostly associated with possible changes of domestic or foreign regulations or policy that can influence power plant operation and long-term fuel availability and price. Two factors that affect decision-making should be distinguished. The first is the total impact of certain non-measurable factor and the other is the impact of certain technology on that non-measurable factor like public impact, for example. The objective of multi-criteria evaluation, after weighting and quantification of all impacts is to determine the most acceptable power system expansion option. In the article a simplified quantification will be made of measurable (investment costs, annual maintenance costs, fuel price, indirect costs of power plants) and non-measurable (public attitude, investor's risk) elements that affect future investment decision. For that purpose possible relative values of non-measurable impacts of different options will be determined (their weights and impact on relative increase of annual

  18. Comparing the sustainability parameters of renewable, nuclear and fossil fuel electricity generation technologies

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Annette; Strezov, Vladimir; Evans, Tim

    2010-09-15

    The sustainability parameters of electricity generation have been assessed by the application of eight key indicators. Photovoltaics, wind, hydro, geothermal, biomass, natural gas, coal and nuclear power have been assessed according to their price, greenhouse gas emissions, efficiency, land use, water use, availability, limitations and social impacts on a per kilowatt hour basis. The relevance of this information to the Australian context is discussed. Also included are the results of a survey on Australian opinions regarding electricity generation, which found that Australian prefer solar electricity above any other method, however coal, biomass and nuclear power have low acceptance.

  19. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Do; Gil, Choong Sup [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1993-12-01

    In nuclear or shielding design analysis for reactors including nuclear facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multigroup constant library using the newly compiled data files and the code systems. As the results of this project, JEF-2.2 which is latest version of Joint Evaluated File developed at OECD/NEA was compiled and COMPLOT and EVALPLOT utility codes were installed in personal computer, which are able to draw ENDF/B-formatted nuclear data for comparison and check. Computer system (NJOY/ACER) for generating continuous energy Monte Carlo code MCNP library was established and the system was validated by analyzing a number of experimental data. (Author).

  20. The evaluated nuclear structure data file: Philosophy, content, and uses

    International Nuclear Information System (INIS)

    Burrows, T.W.

    1990-01-01

    The Evaulated Nuclear Structure Data File (ENSDF) is maintained by the National Nuclear Data Center (NNDC) on behalf of the international Nuclear Structure and Decay Data Network sponsored by the International Atomic Energy Agency, Vienna. Data for A=5 to 44 are extracted from the evaluations published in Nuclear Physics; for A≥45 the file is used to produce the Nuclear Data Sheets. The philosophy and methodology of ENSDF evaluations are outlined, along with the file contents of relevance to radionuclide metrologists; the service available at various nuclear data centers and the NNDC on-line capabilities are also discussed. Application codes have been developed for use with ENSDF, and the program RADLST is used as an example. The interaction of ENSDF evaluation with other evaluations is also discussed. (orig.)

  1. Nuclear plant power up-rate study: feedwater heater evaluations

    International Nuclear Information System (INIS)

    Svensson, Eric; Catapano, Michael; Coakley, Michael; Thomas, Dan

    2014-01-01

    Given today's nuclear industry business climate, it has become common for Utility companies to consider increasing unit capacities through turbine replacement and power up-rates. An integral part of the studies conducted by many towards this end, involve the generation of a set of turbine cycle heat balances with predicted performance parameters for the up-rated condition. Once these tentative operating values are established, it becomes necessary to evaluate the suitability of the existing components within each system to ensure they are capable of continued safe and reliable operation. The ultimate cost for the up-rate, including the cost for any major required modifications or significant replacements is weighed against increased revenue generated from the up-rate over time. Exelon's Peach Bottom Atomic Power Station (PBAPS) is currently planning for an Extended Power up-rate (EPU) for both units. To ensure the existing Feedwater Heaters (FWH) could maintain the operating and transient response margins at the EPU condition, an engineering study was conducted. Powerfect Inc. in conjunction with SPX Heat Transfer LLC were contracted to provide engineering services to analyze the design, thermal performance, reliability and operating conditions at projected EPU conditions. Specifically, to address the following with regard to the station's Feedwater Heaters (FWHs): 1. Evaluate Drain Cooler (DC) Velocities - including zone inlet velocity, cross and window velocities and outlet velocities. 2. Evaluate Drain Cooler Zone Pressure Drop for effect on drain cooler margins to flashing. 3. Evaluate differential pressure allowable across the pass partition plate. 4. Evaluate Drain Cooler Tube Vibration Potential. 5. Perform detailed steam dome velocity calculations. The goal of the study was to identify the most susceptible areas within the heaters for problems and potential failures when operating at the higher duty of the EPU condition for the remaining life

  2. Resonance parameter and covariance evaluation for 16O up to 6 MeV

    Directory of Open Access Journals (Sweden)

    Leal Luiz

    2016-01-01

    Full Text Available A resolved resonance evaluation was performed for 16O in the energy range 0 eV to 6 MeV using the computer code SAMMY resulting in a set of resonance parameters (RPs that describes well the experimental data used in the evaluation. A RP covariance matrix (RPC was also generated. The RP were converted to the evaluated nuclear data file format using the R-Matrix Limited format and the compact format was used to represent the RPC. In contrast to the customary use of RP, which are frequently intended for the generation of total, capture, and scattering cross sections only, the present RP evaluation permits the computation of angle dependent cross sections. Furthermore, the RPs are capable of representing the (n, α cross section from the energy threshold (2.354 MeV of the (n, α reaction to 6 MeV. The intent of this paper is to describe the procedures used in the evaluation of the RP and RPC, the use of the RPC in benchmark calculations and to assess the impact of the 16O nuclear data uncertainties in the calculate dkeff for critical benchmark experiments.

  3. Monte Carlo simulation of nuclear energy study (II). Annual report on Nuclear Code Evaluation Committee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-01-01

    In the report, research results discussed in 1999 fiscal year at Nuclear Code Evaluation Committee of Nuclear Code Research Committee were summarized. Present status of Monte Carlo simulation on nuclear energy study was described. Especially, besides of criticality, shielding and core analyses, present status of applications to risk and radiation damage analyses, high energy transport and nuclear theory calculations of Monte Carlo Method was described. The 18 papers are indexed individually. (J.P.N.)

  4. Economic evaluation of bids for nuclear power plants

    International Nuclear Information System (INIS)

    1976-01-01

    The purpose of the guidebook is to assist an organisation responsible for a nuclear power project in evaluating and establishing an economic order of merit among competing bids. An approximate overall time schedule for a first nuclear power plant project is provided. A schematic outline of technical bid evaluation is given. The basic procedure of economic bid evaluation is outlined, e.g. evaluation of the present worth of all cost items of plant capital investment, of the nuclear cycle, of O and M costs (operation and maintenance costs), and of economic corrections. All these cost items are evaluated for the economic life of the plant and corrected for escalation where applicable

  5. Ageing evaluation model of nuclear reactors structural elements

    International Nuclear Information System (INIS)

    Ziliukas, A.; Jutas, A.; Leisis, V.

    2002-01-01

    In this article the estimation of non-failure probability by random faults on the structural elements of nuclear reactors is presented. Ageing is certainly a significant factor in determining the limits of nuclear plant lifetime or life extensions. Usually the non failure probability rates failure intensity, which is characteristic for structural elements ageing in nuclear reactors. In practice the reliability is increased incorrectly because not all failures are fixed and cumulated. Therefore, the methodology with using the fine parameter of the failures flow is described. The comparison of non failure probability and failures flow is carried out. The calculation of these parameters in the practical example is shown too. (author)

  6. Evaluating Russian Dual-Use Nuclear Exports

    National Research Council Canada - National Science Library

    Bitterman, Blaine S

    2007-01-01

    ...; however, some of its actions contradict its rhetoric. Although Russia's violation of international agreements on nonproliferation is minimal, it is important to understand why Russia transfers nuclear technology...

  7. Study, design and evaluation of nuclear reactor computer control system

    International Nuclear Information System (INIS)

    Menacer, S.

    1988-01-01

    Nuclear reactor control is a complex process that varies with each reactor and there is no universal agreement as to the best type of control system. After the use of conventional systems for a long time, attention turned towards digital techniques in the reactor control system. This interest emerged because of the difficulties faced in the data manipulation, mainly for post-incident analysis. However, it is not sufficient to insert a computer in a system to solve all the data-handling problems and also the insertion of a computer in a real-time system is not without any effect on the overall system. The scope of this thesis is to show the important parameters that have to be taken into account when choosing and evaluate the performances of the selected system

  8. Evaluation of the nuclear security culture

    International Nuclear Information System (INIS)

    Spitalnik, Jorge

    2003-01-01

    The security culture of an organization resides in its workers and it is expressed by the way the personnel that works in a particular organization practice daily its activities. The security culture can be practice in a high or in a low level, but it always exists and it can always be improved. It is based on the security condition and procedures that have been established in the planning phase and in the implementation of a project. After its implantation, in order to avoid deterioration, basically it is necessary to maintain and to bring updated those conditions and procedures through strategies of follow up and control. This process establishes the basis of a program of maintenance and improvement of the Security Culture. Many self-evaluations that have been accomplished at nuclear organizations based on workers perception concerning working conditions and management environment, have permitted objectively determine if the security doctrine, which the organization assure to follow rigorously into its dally activities, is really so (LS)

  9. Evaluation of the perceptual grouping parameter in the CTVA model

    Directory of Open Access Journals (Sweden)

    Manuel Cortijo

    2005-01-01

    Full Text Available The CODE Theory of Visual Attention (CTVA is a mathematical model explaining the effects of grouping by proximity and distance upon reaction times and accuracy of response with regard to elements in the visual display. The predictions of the theory agree quite acceptably in one and two dimensions (CTVA-2D with the experimental results (reaction times and accuracy of response. The difference between reaction-times for the compatible and incompatible responses, known as the responsecompatibility effect, is also acceptably predicted, except at small distances and high number of distractors. Further results using the same paradigm at even smaller distances have been now obtained, showing greater discrepancies. Then, we have introduced a method to evaluate the strength of sensory evidence (eta parameter, which takes grouping by similarity into account and minimizes these discrepancies.

  10. Collection and evaluation of nuclear data of Th-232

    International Nuclear Information System (INIS)

    Osawa, Takaaki

    1979-01-01

    Present status of the requirement to and measurement and evaluation of the nuclear data of Th-232 is presented. The accuracy and energy range of the observed data at present are not enough to the demand from reactor engineering. The data of total cross-section are given in the energy range from 1.5 to 15 MeV from the data by Foster and Fasoli. The data by Uttley for the energy less than 1.5 MeV were accepted. Recently, Whalen and Kobayashi presented new data. Optical potential parameters were deduced. Re-normalization of the capture cross-sections of Th-232 was made on the basis of the evaluated values by Matsunobu and by Kanda. The values are a little smaller than the values in ENDF/B-4. Fission cross-sections were given by Henkel up to 9 MeV, and by Rago and Pankratov for the energy range above 9 MeV. Recently, Behrens presented new data for wide energy range. The accuracy of the measured cross-sections of inelastic scattering is not enough for reactor design. The accurate values of the cross-sections of (n, 2n) reaction of Th-232 have been demanded. Resonance parameters have been measured for wide energy range. In the energy range of thermal neutrons, the capture cross-section is about 7.4 barn. The characteristics of velocity dependence of the capture cross-section in this range should be investigated. (Kato, T.)

  11. Evaluation of thermal-hydraulic parameter uncertainties in a TRIGA research reactor

    International Nuclear Information System (INIS)

    Mesquita, Amir Z.; Costa, Antonio C.L.; Ladeira, Luiz C.D.; Rezende, Hugo C.; Palma, Daniel A.P.

    2015-01-01

    Experimental studies had been performed in the TRIGA Research Nuclear Reactor of CDTN/CNEN to find out the its thermal hydraulic parameters. Fuel to coolant heat transfer patterns must be evaluated as function of the reactor power in order to assess the thermal hydraulic performance of the core. The heat generated by nuclear fission in the reactor core is transferred from fuel elements to the cooling system through the fuel-cladding (gap) and the cladding to coolant interfaces. As the reactor core power increases the heat transfer regime from the fuel cladding to the coolant changes from single-phase natural convection to subcooled nucleate boiling. This paper presents the uncertainty analysis in the results of the thermal hydraulics experiments performed. The methodology used to evaluate the propagation of uncertainty in the results was done based on the pioneering article of Kline and McClintock, with the propagation of uncertainties based on the specification of uncertainties in various primary measurements. The uncertainty analysis on thermal hydraulics parameters of the CDTN TRIGA fuel element is determined, basically, by the uncertainty of the reactor's thermal power. (author)

  12. Thermal-Hydraulic Sensitivity Study of Intermediate Loop Parameters for Nuclear Hydrogen Production System

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Jong Hwa; Lee, Heung Nae; Park, Jea Ho [KONES Corp., Seoul (Korea, Republic of); Lee, Won Jae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, Sang Il; Yoo, Yeon Jae [Hyundai Engineering Co., Seoul (Korea, Republic of)

    2016-10-15

    The heat generated from the VHTR is transferred to the intermediate loop through Intermediate Heat Exchanger (IHX). It is further passed on to the Sulfur-Iodine (SI) hydrogen production system (HPS) through Process Heat Exchanger (PHX). The IL provides the safety distance between the VHTR and HPS. Since the IL performance affects the overall nuclear HPS efficiency, it is required to optimize its design and operation parameters. In this study, the thermal-hydraulic sensitivity of IL parameters with various coolant options has been examined by using MARS-GCR code, which was already applied for the case of steam generator. Sensitivity study of the IL and PHX parameters has been carried out based on their thermal-hydraulic performance. Several parameters for design and operation, such as the pipe diameter, safety distance and surface area, are considered for different coolant options, He, CO{sub 2} and He-CO{sub 2} (2:8). It was found that the circulator work is the major factor affecting on the overall nuclear hydrogen production system efficiency. Circulator work increases with the safety distance, and decreases with the operation pressure and loop pipe diameter. Sensitivity results obtained from this study will contribute to the optimization of the IL design and operation parameters and the optimal coolant selection.

  13. Site-specific parameter values for the Nuclear Regulatory Commission's food pathway dose model

    International Nuclear Information System (INIS)

    Hamby, D.M.

    1992-01-01

    Routine operations at the Savannah River Site (SRS) in Western South Carolina result in radionuclide releases to the atmosphere and to the Savannah River. The resulting radiation doses to the off-site maximum individual and the off-site population within 80 km of the SRS are estimated on a yearly basis. These estimates are currently generated using dose models prescribed for the commercial nuclear power industry by the Nuclear Regulatory Commission (NRC). The NRC provides default values for dose-model parameters for facilities without resources to develop site-specific values. A survey of land- and water-use characteristics for the Savannah River area has been conducted to determine site-specific values for water recreation, consumption, and agricultural parameters used in the NRC Regulatory Guide 1.109 (1977) dosimetric models. These site parameters include local characteristics of meat, milk, and vegetable production; recreational and commercial activities on the Savannah River; and meat, milk, vegetable, and seafood consumption rates. This paper describes how parameter data were obtained at the Savannah River Site and the impacts of such data on off-site dose. Dose estimates using site-specific parameter values are compared to estimates using the NRC default values

  14. Wireless network development for the automatic registration of parameters in laboratories of nuclear analytical techniques

    International Nuclear Information System (INIS)

    Tincopa, Jean Pierre; Baltuano, Oscar; Bedregal, Patricia

    2015-01-01

    This paper presents in detail the development of a low-cost wireless network for automatic recording of temperature and relative humidity parameters in the laboratory of nuclear analytical techniques. This prototype has a DHT22 sensor which gives us both parameters with high precision and are automatically read and displayed by a ATmega328P microcontroller. This data is then transmitted through transceivers Xbee Pro S2B forming a mesh network for real time storage using an RTC (Real Time Clock). We present the experimental results obtained in its implementation. (author)

  15. Nuclear characteristics evaluation for Kyoto University Research Reactor with low-enriched uranium core

    Energy Technology Data Exchange (ETDEWEB)

    Nakajima, Ken; Unesaki, Hironobu [Kyoto University Research Reactor Institute, Kumatori-cho Sennan-gun Osaka (Japan)

    2008-07-01

    A project to convert the fuel of Kyoto University Research Reactor (KUR) from highly enriched uranium (HEU) to low-enriched uranium (LEU) is in progress as a part of RERTR program. Prior to the operation of LEU core, the nuclear characteristics of the core have been evaluated to confirm the safety operation. In the evaluation, nuclear parameters, such as the excess reactivity, shut down margin control rod worth, reactivity coefficients, were calculated, and they were compared with the safety limits. The results of evaluation show that the LEU core is able to satisfy the safety requirements for operation, i.e. all the parameters satisfy the safety limits. Consequently, it was confirmed that the LEU fuel core has the proper nuclear characteristics for the safety operation. (authors)

  16. Atomic and nuclear parameters of single electron capture decaying nuclides; Constantes atomicas y nucleares de nucleidos que se desintegran por captura electronica pura

    Energy Technology Data Exchange (ETDEWEB)

    Grau, A

    1981-07-01

    Atomic and nuclear parameters of the following nuclides which decay by electron capture have been calculated: 37{sup A}r, 41{sup C}a, 49{sup V}, 53{sup M}n, 55{sup F}e,59{sup N}i, 68Ge,82{sup S}r, 97{sup T}c, 118{sup T}e, 131{sup C}s, 137{sup L}a, 140{sup N}d, 157{sup T}b, 165{sup E}r, 193{sup p}t, 194{sup H}g, and 205{sup P}h The evaluation rules are included in the first part of the paper. The values and the associated uncertainties of the following parameters have been tabulated: decay energy, electron capture probabilities, fluorescence yield, electron emission and X-ray emission. (Author) 27 refs.

  17. Evaluation of decision support systems for nuclear accidents

    International Nuclear Information System (INIS)

    Sdouz, G.; Mueck, K.

    1998-05-01

    In order to adopt countermeasures to protect the public after an accident in a nuclear power plant in an appropriate and optimum way, decision support systems offer a valuable assistance in supporting the decision maker in choosing and optimizing protective actions. Such decision support systems may range from simple systems to accumulate relevant parameters for the evaluation of the situation over prediction models for the rapid evaluation of the dose to be expected to systems which permit the evaluation and comparison of possible countermeasures. Since the establishment of a decision support systems obviously is also required in Austria, an evaluation of systems available or in the state of development in other countries or unions was performed. The aim was to determine the availability of decision support systems in various countries and to evaluate them with regard to depth and extent of the system. The evaluation showed that in most industrialized countries the requirement for a decision support system was realized, but in only few countries actual systems are readily available and operable. Most systems are limited to early phase consequences, i.e. dispersion calculations of calculated source terms and the estimation of exposure in the vicinity of the plant. Only few systems offer the possibility to predict long-term exposures by ingestion. Few systems permit also an evaluation of potential countermeasures, in most cases, however, limited to a few short-term countermeasures. Only one system which is presently not operable allows the evaluation of a large number of agricultural countermeasures. In this report the different systems are compared. The requirements with regard to an Austrian decision support system are defined and consequences for a possible utilization of a DSS or parts thereof for the Austrian decision support system are derived. (author)

  18. New perspective in covariance evaluation for nuclear data

    International Nuclear Information System (INIS)

    Kanda, Y.

    1992-01-01

    Methods of nuclear data evaluation have been highly developed during the past decade, especially after introducing the concept of covariance. This makes it utmost important how to evaluate covariance matrices for nuclear data. It can be said that covariance evaluation is just the nuclear data evaluation, because the covariance matrix has quantitatively decisive function in current evaluation methods. The covariance primarily represents experimental uncertainties. However, correlation of individual uncertainties between different data must be taken into account and it can not be conducted without detailed physical considerations on experimental conditions. This procedure depends on the evaluator and the estimated covariance does also. The mathematical properties of the covariance have been intensively discussed. Their physical properties should be studied to apply it to the nuclear data evaluation, and then, in this report, are reviewed to give the base for further development of the covariance application. (orig.)

  19. State and parameter estimation in a nuclear fuel pin using the extended Kalman filter

    International Nuclear Information System (INIS)

    Feeley, J.J.

    1979-03-01

    The Kalman filter is a powerful tool for the design and analysis of stochastic systems. The general nature of the method permits such diverse applications as on-line state estimation in optimal control systems, as well as state and parameter estimation applications in data analysis and system identification. However, while there have been a large number of Kalman filter applications in the aerospace industry, there have been relatively few in the nuclear industry. The report describes some initial efforts made at the Idaho National Engineering Laboratory to gain experience with the methods of Kalman filtering and to test their applicability to nuclear engineering problems. Two specific cases were considered: first, a real-time state estimation problem using a hybrid computer where the process was simulated on the analog portion of the computer, and the Kalman filter was programmed on the digital portion; second, a system identification problem where a digital extended Kalman filter program was used to estimate states and parameters in a nuclear fuel pin using data generated both by actual experiments and computer simulations. The report contains a derivation of the Kalman filter equations, a development of the mathematical model of the nuclear fuel pin, a description of the computer programs used in the analysis, and a discussion of the results obtained

  20. Evaluation of reliability assurance approaches to operational nuclear safety

    International Nuclear Information System (INIS)

    Mueller, C.J.; Bezella, W.A.

    1984-01-01

    This report discusses the results of research to evaluate existing and/or recommended safety/reliability assurance activities among nuclear and other high technology industries for potential nuclear industry implementation. Since the Three Mile Island (TMI) accident, there has been increased interest in the use of reliability programs (RP) to assure the performance of nuclear safety systems throughout the plant's lifetime. Recently, several Nuclear Regulatory Commission (NRC) task forces or safety issue review groups have recommended RPs for assuring the continuing safety of nuclear reactor plants. 18 references

  1. Parameter identification of a BWR nuclear power plant model for use in optimal control

    International Nuclear Information System (INIS)

    Volf, K.

    1976-02-01

    The problem being considered is the modeling of a nuclear power plant for the development of an optimal control system of the plant. Current system identification concepts, combining input/output information with a-priori structural information are employed. Two of the known parameter identification methods i.e., a least squares method and a maximum likelihood technique, are studied as ways of parameter identification from measurement data. A low order state variable stochastic model of a BWR nuclear power plant is presented as an application of this approach. The model consists of a deterministic and a noise part. The deterministic part is formed by simplified modeling of the major plant dynamic phenomena. The moise part models the effects of input random disturbances to the deterministic part and additive measurement noise. Most of the model parameters are assumed to be initially unknown. They are identified using measurement data records. A detailed high order digital computer simulation is used to simulate plant dynamic behaviour since it is not conceivable for experimentation of this kind to be performed on the real nuclear power plant. The identification task consists in adapting the performance of the simple model to the data acquired from this plant simulation ensuring the applicability of the techniques to measurement data acquired directly from the plant. (orig.) [de

  2. Probabilistic Seismic Hazard Characterization and Design Parameters for the Sites of the Nuclear Power Plants of Ukraine

    International Nuclear Information System (INIS)

    Savy, J.B.; Foxall, W.

    2000-01-01

    The U.S. Department of Energy (US DOE), under the auspices of the International Nuclear Safety Program (INSP) is supporting in-depth safety assessments (ISA) of nuclear power plants in Eastern Europe and the former Soviet Union for the purpose of evaluating the safety and upgrades necessary to the stock of nuclear power plants in Ukraine. For this purpose the Hazards Mitigation Center at Lawrence Livermore National Laboratory (LLNL) has been asked to assess the seismic hazard and design parameters at the sites of the nuclear power plants in Ukraine. The probabilistic seismic hazard (PSH) estimates were updated using the latest available data and knowledge from LLNL, the U.S. Geological Survey, and other relevant recent studies from several consulting companies. Special attention was given to account for the local seismicity, the deep focused earthquakes of the Vrancea zone, in Romania, the region around Crimea and for the system of potentially active faults associated with the Pripyat Dniepro Donnetts rift. Aleatory (random) uncertainty was estimated from the available data and the epistemic (knowledge) uncertainty was estimated by considering the existing models in the literature and the interpretations of a small group of experts elicited during a workshop conducted in Kiev, Ukraine, on February 2-4, 1999

  3. Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-08-15

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

  4. Procedures manual for the Evaluated Nuclear Structure Data File

    International Nuclear Information System (INIS)

    Bhat, M.R.

    1987-10-01

    This manual is a collection of various notes, memoranda and instructions on procedures for the evaluation of data in the Evaluated Nuclear Structure Data File (ENSDF). They were distributed at different times over the past few years to the evaluators of nuclear structure data and some of them were not readily avaialble. Hence, they have been collected in this manual for ease of reference by the evaluators of the international Nuclear Structure and Decay Data (NSDD) network contribute mass-chains to the ENSDF. Some new articles were written specifically for this manual and others are reivsions of earlier versions

  5. Evaluation of Waste Arising from Future Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Jubin, Robert Thomas; Taiwo, Temitope; Wigeland, Roald

    2015-01-01

    A comprehensive study was recently completed at the request of the US Department of Energy Office of Nuclear Energy (DOE-NE) to evaluate and screen nuclear fuel cycles. The final report was issued in October 2014. Uranium- and thorium-based fuel cycles were evaluated using both fast and thermal spectrum reactors. Once-through, limited-recycle, and continuous-recycle cases were considered. This study used nine evaluation criteria to identify promising fuel cycles. Nuclear waste management was one of the nine evaluation criteria. The waste generation criterion from this study is discussed herein.

  6. Nuclear power: 2004 world report - evaluation

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    Last year, 2004, 441 nuclear power plants were available for power supply in 31 countries of the world. Nuclear generating capacity attained its highest level so far at an aggregate gross power of 385,854 MWe and an aggregate net power of 366,682 MWe, respectively. Nine different reactor lines are operated in commercial nuclear power plants. Light water reactors (PWR and BWR) again are in the lead with 362 plants. At year's end, 22 nuclear power plants with an aggregate gross power of 18,553 MWe and an aggregate net power, respectively, of 17,591 MWe were under construction in nine countries. Of these, twelve are light water reactors, nine are CANDU-type reactors, and one is a fast breeder reactor. So far, 104 commercial reactors with powers in excess of 5 MWe have been decommissioned in eighteen countries, most of them low-power prototype plants. 228 nuclear power plants of those in operation, i.e. slightly more than half, were commissioned in the 1980es. Nuclear power plant availabilities in terms of capacity and time again reached record levels. Capacity availability was 84.30%, availability in terms of time, 85.60%. The four nuclear power plants in Finland continue to be world champions in this respect with a cumulated average capacity availability of 90.30%. (orig.)

  7. Evaluation method for change of concentration of nuclear fuel material

    International Nuclear Information System (INIS)

    Kiyono, Takeshi; Ando, Ryohei.

    1997-01-01

    The present invention provides a method of evaluating the change of concentration of compositions of nuclear fuel element materials loaded to a reactor along with neutron irradiation based on analytic calculation not relying on integration with time. Namely, the method of evaluating the change of concentration of nuclear fuel materials comprises evaluating the changing concentration of nuclear fuel materials based on nuclear fission, capturing of neutrons and radioactive decaying along with neutron irradiation. In this case, an optional nuclide on a nuclear conversion chain is determined as a standard nuclide. When the main fuel material is Pu-239, it is determined as the standard nuclide. The ratio of the concentration of the standard nuclide to that of the nuclide as an object of the evaluation can be expressed by the ratio of the cross sectional area of neutron nuclear reaction of the standard nuclide to the cross sectional area of the neutron nuclear reaction of the nuclide as the object of the evaluation. Accordingly, the concentration of the nuclide as the object of the evaluation can be expressed by an analysis formula shown by an analysis function for the ratio of the concentration of the standard nuclide to the cross section of the neutron nuclear reaction. As a result, by giving an optional concentration of the standard nuclide to the analysis formula, the concentration of each of other nuclides can be determined analytically. (I.S.)

  8. [Chromosomal instability parameters in the population affected by nuclear explosions at the Semipalatinsk nuclear test site].

    Science.gov (United States)

    Abil'dinova, G Zh; Kuleshov, N P; Sviatova, G S

    2003-08-01

    A population genetic survey of 149 persons who were born and have permanently lived in the contaminated zones of the Semipalatinsk region has been performed. A cytogenetic study has demonstrated that the frequency of aberrant cells is 1.7-3 times higher than control parameters. The total frequencies of chromosome aberrations are 3.43 +/- 0.48, 3.1 +/- 0.3, 1.8 +/- 0.2, and 1.15 +/- 0.17 aberrations per 100 cells in the populations of the extreme radiation risk (ERR), maximum radiation risk (MaxRR), minimum radiation risk (MinRR), and control zones, respectively. The high chromosome aberration rate in all three zones of radiation risk has been detected mainly due to radiation-induced chromosome markers, including paired fragments (1.2 +/- 0.2, 0.94 +/- 0.13, and 0.43 +/- 0.06 per 100 cells, respectively), dicentric and ring chromosomes (0.44 +/- 0.04, 0.45 +/- 0.07, and 0.11 +/- 0.02 per 100 cells, respectively), and stable chromosome aberrations (0.74 +/- 0.16, 0.8 +/- 0.1, and 0.63 +/- 0.13 per 100 cells, respectively). The qualitative spectra of the cytogenetic lesions observed in these groups indicate a mutagenic effect of ionizing radiation on chromosomes in the populations studied.

  9. Evaluation of risk impact of changes to Completion Times addressing model and parameter uncertainties

    International Nuclear Information System (INIS)

    Martorell, S.; Martón, I.; Villamizar, M.; Sánchez, A.I.; Carlos, S.

    2014-01-01

    This paper presents an approach and an example of application for the evaluation of risk impact of changes to Completion Times within the License Basis of a Nuclear Power Plant based on the use of the Probabilistic Risk Assessment addressing identification, treatment and analysis of uncertainties in an integrated manner. It allows full development of a three tired approach (Tier 1–3) following the principles of the risk-informed decision-making accounting for uncertainties as proposed by many regulators. Completion Time is the maximum outage time a safety related equipment is allowed to be down, e.g. for corrective maintenance, which is established within the Limiting Conditions for Operation included into Technical Specifications for operation of a Nuclear Power Plant. The case study focuses on a Completion Time change of the Accumulators System of a Nuclear Power Plant using a level 1 PRA. It focuses on several sources of model and parameter uncertainties. The results obtained show the risk impact of the proposed CT change including both types of epistemic uncertainties is small as compared with current safety goals of concern to Tier 1. However, what concerns to Tier 2 and 3, the results obtained show how the use of some traditional and uncertainty importance measures helps in identifying high risky configurations that should be avoided in NPP technical specifications no matter the duration of CT (Tier 2), and other configurations that could take part of a configuration risk management program (Tier 3). - Highlights: • New approach for evaluation of risk impact of changes to Completion Times. • Integrated treatment and analysis of model and parameter uncertainties. • PSA based application to support risk-informed decision-making. • Measures of importance for identification of risky configurations. • Management of important safety issues to accomplish safety goals

  10. Method of safety evaluation in nuclear power plants

    International Nuclear Information System (INIS)

    Kuraszkiewicz, P.; Zahn, P.

    1988-01-01

    A novel quantitative technique for evaluating safety of subsystems of nuclear power plants based on expert estimations is presented. It includes methods of mathematical psychology recognizing the effect of subjective factors in the expert estimates and, consequently, contributes to further objectification of evaluation. It may be applied to complementing probabilistic safety assessment. As a result of such evaluations a characteristic 'safety of nuclear power plants' is obtained. (author)

  11. Soil structure interaction model and variability of parameters in seismic analysis of nuclear island connected building

    International Nuclear Information System (INIS)

    Subramanian, K.V.; Palekar, S.M.; Bavare, M.S.; Mapari, H.A.; Patel, S.C.; Pillai, C.S.

    2005-01-01

    This paper provides salient features of the Soil Structure Interaction analysis of Nuclear Island Connected Building (NICB). The dynamic analysis of NICB is performed on a full 3D model accounting for the probable variation in the stiffness of the founding medium. A range analyses was performed to establish the effect of variability of subgrade parameters on the results of seismic analyses of NICB. This paper presents details of various analyses with respect to the subgrade model, uncertainties in subgrade properties, results of seismic analyses and a study of effect of the variability of parameters on the results of these analyses. The results of this study indicate that the variability of soil parameters beyond a certain value of shear wave velocity does not influence the response and in fact the response marginally diminishes. (authors)

  12. Evaluated nuclear data file libraries use in nuclear-physical calculations

    International Nuclear Information System (INIS)

    Gritsaj, O.O.; Kalach, N.Yi.; Kal'chenko, O.Yi.; Kolotij, V.V.; Vlasov, M.F.

    1994-01-01

    The necessity of nuclear updated usage is founded for neutron experiment modeling calculations, for preparation of suitable data for reactor calculations and for other applications that account of detail energetic structure of cross section is required. The scheme of system to coordinate the work to collect and to prepare evaluated nuclear data on an international scale is presented. Main updated and recommended nuclear data libraries and associated computer programs are reviewed. Total neutron cross sections for 28 energetic groups calculated on the base of natural mixture iron isotopes evaluated nuclear data file (BROND-2, 1991) have been compared with BNAB-78 data. (author). 7 refs., 1 tab., 4 figs

  13. Chinese evaluated nuclear data library, version 2 (CENDL-2)

    International Nuclear Information System (INIS)

    Cai Dunjiu; Liang Qichang; Liu Tingjin

    1997-01-01

    A complete set of neutron nuclear data for 54 important nuclides from H to 249 Cf has been evaluated and recommended, with the incident neutron energy range from 10 -5 eV to 20 MeV. The main features for CEDNDL-2 are as follows: on the basis of CENDL-1, was carried out the renewal evaluations, extended the energy region, supplemented the data type of evaluations, and added the new evaluations; established the computerized nuclear data library according to the international standard format; improved and developed the related theoretical methods and technology for nuclear data calculations and evaluation processing; developed a complete set of the theoretical calculation codes with new ideas and our own distinguishing features; and formed a complete set of programs for nuclear data processing and benchmark testing. With new experimental data, careful evaluation analysis and theoretical calculations, the evaluations for partial nuclides have our own distinguishing features to give significant improvement compared to the existing world-wide advanced nuclear data libraries. Some evaluations have been adopted by other advanced libraries. The CENDL-2 has been released as one of the five main advanced evaluated nuclear data libraries for users in the world by International Atomic Energy Agency

  14. Study on comprehensive evaluation methods for nuclear fuel cycle

    International Nuclear Information System (INIS)

    Arie, Kazuo

    1999-03-01

    This investigation on comprehensive-evaluation-methods for nuclear fuel cycle has been performed through open-literature search. As the results, no proper comprehensive-evaluation-method has been found which integrate several factors to be considered into only one factor. In the evaluation of future advanced nuclear energy systems, it is required to evaluate from both view points of natural resources and natural environment, in addition to the other factors such as safety, economy, and proliferation resistance. It is recommended that clarification of specific items or targets to be evaluated is most important as the first thing to be done. Second, methodology for the evaluation should be discussed. (author)

  15. 2004 world nuclear power report - evaluation

    International Nuclear Information System (INIS)

    Anon.

    2004-01-01

    Last year, 2003, 439 nuclear power plants were available for electricity generation in 31 countries of the world. With an aggregate gross capacity of 380,489 MWe and an aggregate net capacity of 361,476MWe, nuclear generating capacity reached its highest level so far. Nine different reactor lines are operated in the commercial nuclear power plants. Light water reactors (PWR and BWR) continue to be in the lead with 355 plants. Twenty-nine nuclear power plants with an aggregate gross capacity of 24,222 MWe and an aggregate net capacity of 23,066 MWe were under construction in eleven countries. Of these, twenty are light water reactors, and seven are CANDU-type reactors. Ninety-nine commercial reactors with a capacity in excess of 5 MWe have so far been decommissioned in eighteen countries, most of them prototype plants of low power. 228 plants, i. e. slightly more than half of the number of plants currently in operation, were commissioned in the 1980s. The oldest commercial nuclear power plant in the world, Calder Hall unit 1, was disconnected from the power grid for good in its 48th year of operation in 2003. For the first time in ten years, the availability in terms of time and capacity of nuclear power plants has decreased from 83,80% in 2002 to 80.50%, and from 84.60% to 81.50%, respectively, in 2003. The main causes are prolonged outages of high-capacity plants in Japan as a consequence of administrative restrictions. The four nuclear power plants in Finland continue to be at the top of the list worldwide with a cumulated average availability of capacity of 90.30%. (orig.)

  16. Nuclear power: 2006 world report - evaluation

    International Nuclear Information System (INIS)

    Anon.

    2007-01-01

    Last year, 2006, 437 nuclear power plants were available for power supply in 31 countries, 7 plants less than in 2005. One unit was commissioned for the first time, 8 nuclear power plants were decommissioned for good in 2006. At a cumulated gross power of 389,488 MWe and a cumulated net power of 370,441 MWe, respectively, worldwide nuclear generating capacity has reached a high level so far. Nine different reactor lines are operated in commercial plants: PWR, PWR-VVER, BWR, CANDU, D 2 O PWR, GCR, AGR, LWGR, and LMFBR. Light water reactors (PWR and BWR) continue to top the list with 358 plants. By the end of the year, 10 countries operated 29 nuclear power plants with an aggregate gross power of 25,367 MWe and an aggregate net power of 23,953 MWe, respectively. Of these, 21 are light water reactors, 5 are CANDU-type reactors, 2 are fast breeder and 1 a LWGR. 123 commercial reactors with an aggregate power in excess of 5 MWe have so far been decommissioned in 19 countries. Most of them are prototype plants of low power. About 70% of the nuclear power plants in operation, namely 304 plants, were commissioned in the eighties and nineties. The energy availability and operating availability factors of the nuclear power plants again reached peak levels: 82% for energy availability, and 83% for operating availability. The 4 nuclear power plants in Finland continue to be in the lead worldwide with a cumulated average operating capacity factor of 94%. (orig.)

  17. Nuclear power. 2008 world report - evaluation

    International Nuclear Information System (INIS)

    Anon.

    2010-01-01

    In 2008, 438 nuclear power plants were available for power supply in 31 countries, 1 plant less than in 2007. No unit was commissioned for the first time, 1 nuclear power plant was decommissioned for good in 2008. At a cumulated gross power of 392,597 MWe and a cumulated net power of 372,170 MWe, respectively, worldwide nuclear generating capacity has reached a high level. Nine different reactor lines are operated in commercial plants: PWR, PWR-VVER, BWR, CANDU, D2O PWR, GCR, AGR, LWGR, and LMFBR. Light water reactors (PWR and BWR) continue to top the list with 358 plants. By the end of 2008, in 14 countries 43 nuclear power plants with an aggregate gross power of 39,211 MWe and an aggregate net power of 36,953 MWe were under construction. Of these, 37 are light water reactors, 3 are CANDU-type reactors, 2 are fast breeder and 1 D2O-PWR. 124 commercial reactors with an aggregate power in excess of 5 MWe have so far been decommissioned in 19 countries. Most of them are prototype plants of low power. About 70% of the nuclear power plants in operation, namely 304 plants, were commissioned in the eighties and nineties. The energy availability and operating availability factors of the nuclear power plants reached good levels: 80.80% for operating availability and 80,00% for energy availability. The four nuclear power plants in Finland continuecontinue to be in the lead worldwide with a cumulated average operating capacity factor of 91,60%. (orig.)

  18. 2002 Nuclear Power World Report - Evaluation

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    Last year, in 2002, 441 nuclear power plants were available for power supply in 31 countries in the world. With an aggregate gross power of 377,359 MWe, and an aggregate net power of 359,429 MWe, respectively, the nuclear generating capacity reached its highest level so far. Nine different reactor lines are used in commercial facilities. Light water reactors (PWR and BWR) contribute 355 plants, which makes them the most common reactor line. In twelve countries, 32 nuclear power plants with an aggregate gross power of 26,842 MWe and an aggregate net power of 25,546 MWe, respectively, are under construction. Of these, 25 units are light water reactors while eight are CANDU-type plants. In eighteen countries, 94 commercial reactors with more than 5 MWe power have been decommissioned so far. Most of these plants are prototypes with low powers. 228 of the nuclear power plants currently in operation, i.e. slightly more than half of them, were commissioned in the eighties. The oldest commercial nuclear power plant, Calder Hall unit 1, supplied power into the public grid in its 47th year of operation in 2002. The availability in terms of time and capacity of nuclear power plants rose from 74.23% in 1991 to 83.40% in 2001. A continued rise to approx. 85% is expected for 2002. In the same way, the non-availability in terms of time (unscheduled) dropped from 6.90% to 3.48%. The four nuclear power plants in Finland are the world's leaders with a cumulated average capacity availability of 90.00%. (orig.) [de

  19. Test facilities for evaluating nuclear thermal propulsion systems

    International Nuclear Information System (INIS)

    Beck, D.F.; Allen, G.C.; Shipers, L.R.; Dobranich, D.; Ottinger, C.A.; Harmon, C.D.; Fan, W.C.; Todosow, M.

    1992-01-01

    Interagency panels evaluating nuclear thermal propulsion (NTP) development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and baseline performance of some of the major subsystems designed to support a proposed ground test complex for evaluating nuclear thermal propulsion fuel elements and engines being developed for the Space Nuclear Thermal Propulsion (SNTP) program. Some preliminary results of evaluating this facility for use in testing other NTP concepts are also summarized

  20. Water hammer in USA nuclear power plants and it's evaluation

    International Nuclear Information System (INIS)

    Liu Shuqian.

    1987-01-01

    The results of evaluations about the water hammer events in USA nuclear power plants in recent years are summarily reported. The evaluations included underlying causes and frequency of water hammer events, damages incurred and systems affected. Through the evaluations about water hammer events and on the basis of past operation experiences in nuclear power plants, the design and operational modifications to prevent or mitigate water hammer events were presented. The NRC's current opinions relating to the water hammer problems are summarized, the importance of water hammer events for nuclear power plants construction in China is indicated

  1. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

    2013-09-30

    This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

  2. Evaluation of Critical Parameters to Improve Slope Drainage System

    Directory of Open Access Journals (Sweden)

    Yong Weng Long

    2017-01-01

    Full Text Available This study focuses on identifying and evaluating critical parameters of various drainage configurations, arrangement, and filter which affect the efficiency of water draining system in slopes. There are a total of seven experiments with different types of homogeneous soil, drainage envelope, filter material, and quantity of pipes performed utilizing a model box with a dimension of 0.8 m × 0.8 m × 0.6 m. The pipes were orientated at 5 degrees from the horizontal. Rainfall event was introduced via a rainfall simulator with rainfall intensity of 434.1 mm/h. From the experiments performed, the expected outcomes when utilizing double pipes and geotextile as envelope filter were verified in this study. The results obtained from these experiments were reviewed and compared with Chapter 14 “Subsurface Drainage Systems” of DID’s Irrigation and Agricultural Drainage Manual of Malaysia and the European standard. It is recommended that the pipe installed in the slope could be wrapped with geotextile and in tandem with application of granular filter to minimize clogging without affecting the water discharge rate. Terzaghi’s filter criteria could be followed closely when deciding on new materials to act as aggregate filter. A caging system could be introduced as it could maintain the integrity of the drainage system and could ease installation.

  3. Evaluating the parameters of a mobile maize dryer in practice

    Directory of Open Access Journals (Sweden)

    Josef Los

    2013-01-01

    Full Text Available The method of drying maize for grain has been recently employed on a large scale in the Czech Republic not only thanks to new maize hybrids but also thanks to the existence of new models of drying plants. One of the new post-harvest lines is a plant in Lipoltice (mobile dryer installed in 2010, storage base in 2012 where basic operational measurements were made of the energy intensiveness of drying and operating parameters of the maize dryer were evaluated. The process of maize drying had two stages, i.e. pre-drying from the initial average grain humidity of 28.55% to 19.6% in the first stage, and the additional drying from 16.7% to a final storage grain humidity of 13.7%. Mean volumes of natural gas consumed per 1 t% for drying in the first and second stage amounted to 1.275 m3 and 1.56 m3, respectively. The total mean consumption of electric energy per 1 t% was calculated to be 1.372 kWh for the given configuration of the post-harvest line.

  4. Second Meeting for Evaluation of the Nuclear Safety Convention

    International Nuclear Information System (INIS)

    2002-01-01

    This report presents the results of the Second Meeting for Evaluation of the Nuclear Safety Convention. the CSN. as the only competent Government organism on nuclear safety, represented Spain in the preparation of the national report and at the Review Meeting, acquiring a set of obligations for the next three years, until the holding of third meeting. (Author)

  5. Contribution to evaluating nuclear power plant accidents

    International Nuclear Information System (INIS)

    Razga, J.; Horacek, P.

    1990-01-01

    Large-scale accidents pose the highest risk in the use of nuclear power. They are the major factor that has to be taken into account when assessing the effect of nuclear power plants on human health and on the environment. In Czechoslovak conditions, the effectiveness of provisions made to reduce the hazard of large-scale nuclear power plant accidents must be considered from the following aspects: effect on human health, consequences of long-term disabling of the infrastructure, potential of human and material reserves in coping with the accident, consequences of power failure for the electricity system, effect on agricultural production and catering, risk of ground and surface water contamination in the Labe or Danube river basin, and international political aspects. (Z.M.). 3 tabs., 18 refs

  6. Harvesting rockfall hazard evaluation parameters from Google Earth Street View

    Science.gov (United States)

    Partsinevelos, Panagiotis; Agioutantis, Zacharias; Tripolitsiotis, Achilles; Steiakakis, Chrysanthos; Mertikas, Stelios

    2015-04-01

    Rockfall incidents along highways and railways prove extremely dangerous for properties, infrastructures and human lives. Several qualitative metrics such as the Rockfall Hazard Rating System (RHRS) and the Colorado Rockfall Hazard Rating System (CRHRS) have been established to estimate rockfall potential and provide risk maps in order to control and monitor rockfall incidents. The implementation of such metrics for efficient and reliable risk modeling require accurate knowledge of multi-parametric attributes such as the geological, geotechnical, topographic parameters of the study area. The Missouri Rockfall Hazard Rating System (MORH RS) identifies the most potentially problematic areas using digital video logging for the determination of parameters like slope height and angle, face irregularities, etc. This study aims to harvest in a semi-automated approach geometric and qualitative measures through open source platforms that may provide 3-dimensional views of the areas of interest. More specifically, the Street View platform from Google Maps, is hereby used to provide essential information that can be used towards 3-dimensional reconstruction of slopes along highways. The potential of image capturing along a programmable virtual route to provide the input data for photogrammetric processing is also evaluated. Moreover, qualitative characterization of the geological and geotechnical status, based on the Street View images, is performed. These attributes are then integrated to deliver a GIS-based rockfall hazard map. The 3-dimensional models are compared to actual photogrammetric measures in a rockfall prone area in Crete, Greece while in-situ geotechnical characterization is also used to compare and validate the hazard risk. This work is considered as the first step towards the exploitation of open source platforms to improve road safety and the development of an operational system where authorized agencies (i.e., civil protection) will be able to acquire near

  7. Digitized operator evaluation system for main control room of nuclear power plant

    International Nuclear Information System (INIS)

    Chen Yu; Yan Shengyuan; Chen Wenlong

    2014-01-01

    In order to evaluate the human-machine system matching relation of main control room in nuclear power plant accurately and efficiently, the expression and parameters of operator human body model were analyzed, and the evaluation required function of digital operator was determined. Based on the secondary development technology, the digital operator evaluation body model was developed. It could choose generation, gender, operation posture, single/eyes horizon, and left/right hand up to the domain according to the needs of specific evaluation, it was used to evaluate whether display information can be visible and equipment can be touch, and it also has key evaluation functions such as workspace and character visibility at the same time. The examples show that this method can complete the evaluation work of human-machine matching relation for main control room of nuclear power plant accurately, efficiently and quickly, and achieve the most optimal human-machine coordination relationship. (authors)

  8. Relationships between nuclear magnetic resonance parameters used to characterize weathering spilled oil and soil toxicity in central Patagonia.

    Science.gov (United States)

    Ríos, Stella Maris; Barquin, Mercedes; Katusich, Ofelia; Nudelman, Norma

    2014-01-01

    Oil spill in the Central Patagonian zone was studied to evaluate if any relationship exists between the parameters used to characterize weathering spilled oil and soil toxicity for two plant species and to evaluate if the phytotoxicity to local species would be a good index for the soil contamination. Nuclear magnetic resonance (NMR) structural indexes and column chromatography compositional indexes were determined to characterize the oil spill in the soil samples. Bioassays were also carried out using Lactuca sativa L (reference) and Atriplex lampa (native species) as test organisms. Measurements of the total petroleum hydrocarbon (TPH) and the electrical conductivity (EC) of the soil were carried out to evaluate the effect on the bioassays. The principal components analysis of the parameters determined by NMR, compositional indexes, EC, TPH, and toxicology data shows that the first three principal components accounted for the 78% of the total variance (40%, 25%, and 13% for the first, second, and third PC, respectively). A good agreement was found between information obtained by compositional indexes and NMR structural indexes. Soil toxicity increases with the increase of EC and TPH. Other factors, such as, the presence of branched and aromatic hydrocarbons is also significant. The statistical evaluation showed that the Euclidean distances (3D) between the background and each one of the samples might be a better indicator of the soil contamination, compared with chemical criterion of TPH.

  9. Evaluation of radiation protection in nuclear medicine diagnostic procedures

    International Nuclear Information System (INIS)

    Mohammed, Ezzeldien Mohammed Nour

    2013-05-01

    This study conducted to evaluate the radiation protection in nuclear medicine diagnostic procedures in four nuclear medicine departments in Sudan. The evaluated procedures followed in these departments were in accordance with the standards, International Recommendations and code of practice for radiation protection in nuclear medicine. The evolution included the optimum design for diagnostic nuclear medicine departments, dealing with radioactive sources, quality assurance and quality control, training and responsibilities for radiation worker taking into account economic factors in Sudan. Evaluation of radiation protection procedures in diagnostic investigations was carried out by taken direct measurements of dose rate and the contamination level in some areas where radiation sources, radiation workers and public are involved. Designated questionnaires covered thirteen areas of radiation protection based on inspection check list for nuclear medicine prepared by the International Atomic Energy Agency (IAEA) and American Association of Physicist in Medicine (AAPM) were used in the evaluation. This questionnaire has been Filled by Radiation Protection Officer (RPO), nuclear medicine technologist, nuclear medicine specialist in the nuclear medicine departments. Four hospitals, two governmental hospital and two private hospitals, have been assisted, the assessment shows that although the diagnostic nuclear medicine department in Sudan are not applying a fully safety and radiation protection procedures, but the level of radiation dose and the contamination level were found within acceptable limits. The private hospital D scored the higher level of protection (85.25%) while the governmental hospital C scored the lower level of protection (59.02%). Finally, this study stated some recommendations that if implemented could improve the level of radiation protection in nuclear medicine department. One of the most important recommendations is that a proper radiation protection

  10. Verification and uncertainty evaluation of CASMO-3/MASTER nuclear analysis system

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jae Seung; Cho, Byung Oh; Joo, Han Kyu; Zee, Sung Quun; Lee, Chung Chan; Park, Sang Yoon

    2000-06-01

    MASTER is a nuclear design code developed by KAERI. It uses group constants generated by CASMO-3 developed by Studsvik. In this report the verification and evaluation of uncertainty were performed for the code system application in nuclear reactor core analysis and design. The verification is performed via various benchmark comparisons for static and transient core condition, and core follow calculations with startup physics test predictions of total 14 cycles of pressurized water reactors. Benchmark calculation include comparisons with reference solutions of IAEA and OECA/NEA problems and critical experiment measurements. The uncertainty evaluation is focused to safety related parameters such as power distribution, reactivity coefficients, control rod worth and core reactivity. It is concluded that CASMO-3/MASTER can be applied for PWR core nuclear analysis and design without any bias factors. Also, it is verified that the system can be applied for SMART core, via supplemental comparisons with reference calculations by MCNP which is a probabilistic nuclear calculation code.

  11. Review of ENDF/B-VI Fission-Product Cross Sections[Evaluated Nuclear Data File

    Energy Technology Data Exchange (ETDEWEB)

    Wright, R.Q.; MacFarlane, R.E.

    2000-04-01

    In response to concerns raised in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 93-2, the US Department of Energy (DOE) developed a comprehensive program to help assure that the DOE maintain and enhance its capability to predict the criticality of systems throughout the complex. Tasks developed to implement the response to DNFSB recommendation 93-2 included Critical Experiments, Criticality Benchmarks, Training, Analytical Methods, and Nuclear Data. The Nuclear Data Task consists of a program of differential measurements at the Oak Ridge Electron Linear Accelerator (ORELA), precise fitting of the differential data with the generalized least-squares fitting code SAMMY to represent the data with resonance parameters using the Reich-Moore formalism along with covariance (uncertainty) information, and the development of complete evaluations for selected nuclides for inclusion in the Evaluated Nuclear Data File (ENDFB).

  12. Verification and uncertainty evaluation of CASMO-3/MASTER nuclear analysis system

    International Nuclear Information System (INIS)

    Song, Jae Seung; Cho, Byung Oh; Joo, Han Kyu; Zee, Sung Quun; Lee, Chung Chan; Park, Sang Yoon

    2000-06-01

    MASTER is a nuclear design code developed by KAERI. It uses group constants generated by CASMO-3 developed by Studsvik. In this report the verification and evaluation of uncertainty were performed for the code system application in nuclear reactor core analysis and design. The verification is performed via various benchmark comparisons for static and transient core condition, and core follow calculations with startup physics test predictions of total 14 cycles of pressurized water reactors. Benchmark calculation include comparisons with reference solutions of IAEA and OECA/NEA problems and critical experiment measurements. The uncertainty evaluation is focused to safety related parameters such as power distribution, reactivity coefficients, control rod worth and core reactivity. It is concluded that CASMO-3/MASTER can be applied for PWR core nuclear analysis and design without any bias factors. Also, it is verified that the system can be applied for SMART core, via supplemental comparisons with reference calculations by MCNP which is a probabilistic nuclear calculation code

  13. Multi-objective genetic algorithm parameter estimation in a reduced nuclear reactor model

    Energy Technology Data Exchange (ETDEWEB)

    Marseguerra, M.; Zio, E.; Canetta, R. [Polytechnic of Milan, Dept. of Nuclear Engineering, Milano (Italy)

    2005-07-01

    The fast increase in computing power has rendered, and will continue to render, more and more feasible the incorporation of dynamics in the safety and reliability models of complex engineering systems. In particular, the Monte Carlo simulation framework offers a natural environment for estimating the reliability of systems with dynamic features. However, the time-integration of the dynamic processes may render the Monte Carlo simulation quite burdensome so that it becomes mandatory to resort to validated, simplified models of process evolution. Such models are typically based on lumped effective parameters whose values need to be suitably estimated so as to best fit to the available plant data. In this paper we propose a multi-objective genetic algorithm approach for the estimation of the effective parameters of a simplified model of nuclear reactor dynamics. The calibration of the effective parameters is achieved by best fitting the model responses of the quantities of interest to the actual evolution profiles. A case study is reported in which the real reactor is simulated by the QUAndry based Reactor Kinetics (Quark) code available from the Nuclear Energy Agency and the simplified model is based on the point kinetics approximation to describe the neutron balance in the core and on thermal equilibrium relations to describe the energy exchange between the different loops. (authors)

  14. Multi-objective genetic algorithm parameter estimation in a reduced nuclear reactor model

    International Nuclear Information System (INIS)

    Marseguerra, M.; Zio, E.; Canetta, R.

    2005-01-01

    The fast increase in computing power has rendered, and will continue to render, more and more feasible the incorporation of dynamics in the safety and reliability models of complex engineering systems. In particular, the Monte Carlo simulation framework offers a natural environment for estimating the reliability of systems with dynamic features. However, the time-integration of the dynamic processes may render the Monte Carlo simulation quite burdensome so that it becomes mandatory to resort to validated, simplified models of process evolution. Such models are typically based on lumped effective parameters whose values need to be suitably estimated so as to best fit to the available plant data. In this paper we propose a multi-objective genetic algorithm approach for the estimation of the effective parameters of a simplified model of nuclear reactor dynamics. The calibration of the effective parameters is achieved by best fitting the model responses of the quantities of interest to the actual evolution profiles. A case study is reported in which the real reactor is simulated by the QUAndry based Reactor Kinetics (Quark) code available from the Nuclear Energy Agency and the simplified model is based on the point kinetics approximation to describe the neutron balance in the core and on thermal equilibrium relations to describe the energy exchange between the different loops. (authors)

  15. Heuristic learning parameter identification for surveillance and diagnostics of nuclear power plants

    International Nuclear Information System (INIS)

    Machado, E.L.

    1983-01-01

    A new method of heuristic reinforcement learning was developed for parameter identification purposes. In essence, this new parameter identification technique is based on the idea of breaking a multidimensional search for the minimum of a given functional into a set of unidirectional searches in parameter space. Each search situation is associated with one block in a memory organized into cells, where the information learned about the situations is stored (e.g. the optimal directions in parameter space). Whenever the search falls into an existing memory cell, the system chooses the learned direction. For new search situations, the system creates additional memory cells. This algorithm imitates the following cognitive process: 1) characterize a situation, 2) select an optimal action, 3) evaluate the consequences of the action, and 4) memorize the results for future use. As a result, this algorithm is trainable in the sense that it can learn from previous experience within a specific class of parameter identification problems

  16. Report of evaluation of organization. Japan Nuclear Cycle Development Institute

    International Nuclear Information System (INIS)

    2004-08-01

    Various activities of JNC (Japan Nuclear Cycle Development Institute) from December in 2003 to July in 2004 are evaluated on management, practice and progressing of development of research by the committee on organization evaluation. The report includes abstract, purpose of evaluation, evaluation items, deliberation process, total results of evaluation, development of projects, the spread of results, international cooperation, management system, effort to safety, responsibility of explanation, live together with community and other suggestions. Main projects consists of practice of FBR, development of uranium enrichment, nuclear fuel reprocessing and MOX fuel processing technology, reopening of MONJU, development of high-level radioactive waste and environmental protection policy. (S.Y.)

  17. Stereologic, histopathologic, flow cytometric, and clinical parameters in the prognostic evaluation of 74 patients with intraoral squamous cell carcinomas

    DEFF Research Database (Denmark)

    Bundgaard, T; Sørensen, Flemming Brandt; Gaihede, M

    1992-01-01

    , tumor size, and the TNM classification. RESULTS: The investigation showed a significant difference between the volume-weighted mean nuclear volume (nuclear vv) of oral leukoplakia (n = 29) and oral squamous cell carcinomas (P = 0.001). The value of the parameters as prognostic indicators of survival......BACKGROUND AND METHODS: A consecutive series of all 78 incident cases of intraoral squamous cell carcinoma occurring during a 2-year period in a population of 1.4 million inhabitants were evaluated by histologic score (the modified classification of Jacobsson et al.), flow cytometry, stereology...

  18. Evaluation of nuclear knowledge management: An outcome in JAERI

    International Nuclear Information System (INIS)

    Yanagisawa, K.

    2006-01-01

    The author performed an ex post evaluation on the nuclear research of JAERI and revealed that the national funds invested in this field were 4 b$. With aid of NKM, it was revealed that the total outcome was 6 b$, where the creation of nuclear markets for electricity and nuclear facilities was the main stream. This implies that the cost benefit effect is 6 b$/4 b$ = 1.5 (>1). From this, it can be concluded that JAERI contributes not only to technological promotion of nuclear activity but also to the increase of gross domestic product (GDP). (author)

  19. Evaluation of Visual and Landscape Impacts of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Algohary, S.A.

    2007-01-01

    The nuclear power plant is a huge structure, and in terms of both size and function may result in an unacceptable visual conflict in both local and wider environment. Also, it has major implications in terms of physical, social, economic, environmental and impact on people. The environmental impacts include the visual and landscape aspects of these plants. This paper outlines the main general ideas of the architecture aspects of nuclear power plants, nuclear reactors. Also, it discusses the site selection considerations: Finally, it introduces an approach for the evaluation of visual and landscape impacts of nuclear power plants

  20. Study on Developing Degradation Model for Nuclear Power Plants With Ageing Elements Affected on Operation Parameter

    International Nuclear Information System (INIS)

    Choi, Yong Won; Lim, Sung Won; Lee, Un Chul; Kim, Man Woong; Kim, Kab; Ryu, Yong Ho

    2009-01-01

    As a part of development the evaluation system of safety margin effects for degradation of CANDU reactors, it is required that the degradation model represents the distribution of each ageing factor's value during operating year. Unfortunately, it is not easy to make an explicit relation between the RELAP-CANDU parameters and ageing mechanism because of insufficient data and lack of applicable models. So, operating parameter related with ageing is used for range determination of ageing factor. Then, relation between operating parameter and ageing elements is analyzed and ageing constant values for degradation model are determined. Also the other ageing factor is derived for more accurate ageing analysis

  1. Parameters-adjustable front-end controller in digital nuclear measurement system

    International Nuclear Information System (INIS)

    Hao Dejian; Zhang Ruanyu; Yan Yangyang; Wang Peng; Tang Changjian

    2013-01-01

    Background: One digitizer is used to implement a digital nuclear measurement for the acquisition of nuclear information. Purpose: A principle and method of a parameter-adjustable front-end controller is presented for the sake of reducing the quantitative errors while getting the maximum ENOB (effective number of bits) of ADC (analog-to-digital converter) during waveform digitizing, as well as reducing the losing counts. Methods: First of all, the quantitative relationship among the radiation count rate (n), the amplitude of input signal (V in ), the conversion scale of ADC (±V) and the amplification factor (A) was derived. Secondly, the hardware and software of the front-end controller were designed to fulfill matching the output of different detectors, adjusting the amplification linearly through the control of channel switching, and setting of digital potentiometer by CPLD (Complex Programmable Logic Device). Results: (1) Through the measurement of γ-ray of Am-241 under our digital nuclear measurement set-up with CZT detector, it was validated that the amplitude of output signal of detectors of RC feedback type could be amplified linearly with adjustable amplification by the front-end controller. (2) Through the measurement of X-ray spectrum of Fe-5.5 under our digital nuclear measurement set-up with Si-PIN detector, it was validated that the front-end controller was suitable for the switch resetting type detectors, by which high precision measurement under various count rates could be fulfilled. Conclusion: The principle and method of the parameter-adjustable front-end controller presented in this paper is correct and feasible. (authors)

  2. Nuclear Science References as a Tool for Data Evaluation

    International Nuclear Information System (INIS)

    Winchell, D.F.

    2005-01-01

    For several decades, the Nuclear Science References database has been maintained as a tool for data evaluators and for the wider pure and applied research community. This contribution will describe the database and recent developments in web-based access

  3. Source list of nuclear data bibliographies, compilations, and evaluations

    International Nuclear Information System (INIS)

    Burrows, T.W.; Holden, N.E.

    1978-10-01

    To aid the user of nuclear data, many specialized bibliographies, compilations, and evaluations have been published. This document is an attempt to bring together a list of such publications with an indication of their availability and cost

  4. ENDL-1978. LLL evaluated Nuclear Data Library 1978

    International Nuclear Information System (INIS)

    1979-07-01

    The contents and documentation of the 1978 version of the Evaluated Nuclear Data Library of the Lawrence Livermore Laboratory, USA are summarized. The Library contains numerical neutron reaction data for 88 isotopes or elements

  5. ENSL and CDRL: evaluated nuclear structure libraries

    International Nuclear Information System (INIS)

    Howerton, R.J.

    1981-01-01

    Two files of nuclear structure data derived largely from the seventh edition of the Table of Isotopes are described. The files are computer oriented, and have been constructed so that every decay can be traced either to an eventual ground state or to a positive flag that indicates nothing is known about further decay. 1 table

  6. Evaluating nuclear power: voter choice on the California nuclear energy initiative. Executive summary

    International Nuclear Information System (INIS)

    Hensler, D.R.; Hensler, C.P.

    1979-07-01

    In 1976, under grants from the National Science Foundation and the Ford Foundation, The Rand Corporation conducted a set of surveys of Californians' attitudes toward nuclear power nd Proposition 15 that we hoped would illuminate the reasons for the voters' decision on the nuclear initiative. The study focused on the attitudes of the general public; it did not investigate the factors that motivate activists on both sides of the nuclear controversy. The study was limited to California, but because results indicate that attitudes of Californians are similar to attitudes reported in nationwide surveys, we believe that our findings have broader applicability. The objectives of the study were to: describe public knowledge, beliefs, and evaluation of nuclear energy development; analyze the relationship between beliefs and evaluation of nuclear energy; investigate the relationship between critical beliefs about nuclear energy and general political orientations, trust in government and other political and social institutions, and social background characteristics; describe public knowledge, beliefs, and evaluation of Proposition 15, the California nuclear energy initiative; and investigate the relationship between individuals' voting decisions on Proposition 15 and their evaluations of nuclear power and responses to the initiative campaign

  7. Workshop on nuclear structure and decay data evaluation. Summary report

    International Nuclear Information System (INIS)

    Pronyaev, V.G.; Nichols, A.L.

    2003-01-01

    A summary is given of the aims and contents of the Workshop on Nuclear Structure and Decay Data (NSDD) Evaluation, including the agenda, lists of participants and their presentations, general comments and recommendations. The 1-week workshop was organized by the IAEA Nuclear Data Section, and held in Vienna, Austria, from 18 to 22 November 2002. Workshop material, including participants' presentations, computer codes, manuals and other materials for NSDD evaluators, are freely available on CD-ROM on request. (author)

  8. Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation

    International Nuclear Information System (INIS)

    Bess, John D.; Briggs, J. Blair; Nigg, David W.

    2009-01-01

    One of the challenges that today's new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills.

  9. Evaluation and surveillance of radioactive releases of nuclear installations

    International Nuclear Information System (INIS)

    Hartmann, Ph.

    2002-01-01

    The two days organised by the section Environment of the SFRP have to objective to connect experts in radiation protection in order to debate around the following questions: the actual evaluations modes of releases impacts from nuclear installations, the organisation of the surveillance, to favour the implication of local actors in the evaluation and surveillance around nuclear facilities, the evolutions to envisage. (N.C.)

  10. CRECTJ: a computer program for compilation of evaluated nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1999-09-01

    In order to compile evaluated nuclear data in the ENDF format, the computer program CRECTJ has been developed. CRECTJ has two versions; CRECTJ5 treats the data in the ENDF/B-IV and ENDF/B-V format, and CRECTJ6 the data in the ENDF-6 format. These programs have been frequently used to make Japanese Evaluated Nuclear Data Library (JENDL). This report describes input data and examples of CRECTJ. (author)

  11. An overview of the evaluations of nuclear power by Canadians

    International Nuclear Information System (INIS)

    Barrados, Maria

    1980-01-01

    Limited data are available on Canadian evaluations of nuclear power. General observations are made, based on a 1976 national study by B. Greer-Wootten and a 1978 Canadian Gallup Poll survey. Little change in the knowledge Canadians have of nuclear power appears to have taken place. A sizeable proportion of the population is willing to offer an opinion about the use of nuclear power while knowing nothing about it. Increased knowledge is not associated with more positive or negative evaluations of nuclear power. In more specific evaluations of nuclear safety, increased knowledge is found to be associated with a lowered confidence in the safety of Canadian reactors. There appears to have been a drop in the proportions of Canadians somewhat in favour of nuclear power between 1976 and 1978. Since many Canadians do not know much about the use of nuclear power and the majority of opinions are not strongly committed, there is considerable potential for fluctuation in these figures. Increased emphasis appears to be put on waste management issues in 1978, while nuclear power plants are less likely to be perceived as unsafe. This may be the result of increased discussion of Canadian power reactors. (LL)

  12. Selected environmental considerations and their measuring parameters for nuclear power plant siting

    International Nuclear Information System (INIS)

    Norris, J.A.

    1975-01-01

    The site selection process for nuclear power stations encompasses a broad range of considerations. A categorization of these considerations consistent with the needs of the U. S. Atomic Energy Commission, as the regulatory agency, and of the utility company involves these major areas of concern. They are issues related to safety, environmental impact, and engineering/economics. The more important environmental considerations and their measuring parameters presented in this paper include biota, ecological systems and water quality, land use, aesthetics, water availability, and meteorology. (U.S.)

  13. Sensitivity of control times in function of core parameters and oscillations control in thermal nuclear systems

    International Nuclear Information System (INIS)

    Amorim, E.S. do; D'Oliveira, A.B.; Galvao, O.B.; Oyama, K.

    1981-03-01

    Sensitivity of control times to variation of a thermal reactor core parameters is defined by suitable changes in the power coefficient, core size and fuel enrichment. A control strategy is developed based on control theory concepts and on considerations of the physics of the problem. Digital diffusion theory simulation is described which tends to verify the control concepts considered, face dumped oscillations introduced in one thermal nuclear power system. The effectivity of the control actions, in terms of eliminating oscillations, provided guidelines for the working-group engaged in the analysis of the control rods and its optimal performance. (Author) [pt

  14. Fast dose assessment models, parameters and code under accident conditions for Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zhang, Z.Y.; Hu, E.B.; Meng, X.C.; Zhang, Y.; Yao, R.T.

    1993-01-01

    According to requirement of accident emergency plan for Qinshan Nuclear Power Plant, a Gaussian straight-line model was adopted for estimating radionuclide concentration in surface air. In addition, the effects of mountain body on atmospheric dispersion was considered. By combination of field atmospheric dispersion experiment and wind tunnel modeling test, necessary modifications have been done for some models and parameters. A computer code for assessment was written in Quick BASIC (V4.5) language. The radius of assessment region is 10 km and the code is applicable to early accident assessment. (1 tab.)

  15. Development of supplier evaluation model applying in nuclear power plants

    International Nuclear Information System (INIS)

    Wang Yonggang; Fang Chunfa

    2006-01-01

    It is essential for the safe and stable operations of Nuclear Power Plants that various resources in the supply chain are effectively managed. Supplier is a significant resource of nuclear entities serving as an extension of the operation process. Scientific and radiation evaluation of the performance of suppliers is of vital importance to an effective and high quality supply chain. This paper establishes an advance and practical supplier evaluation system that is applicable for the operational nuclear power plants, based on the analysis of the current operation status of Daya Bay Nuclear Power Station against its targeted objectives, the acquisition of relevant practices home and abroad and the benchmarking with advanced peers, in order to enhance the core competence of nuclear power plant. (authors)

  16. Experimental (Network) and Evaluated Nuclear Reaction Data at NDS

    International Nuclear Information System (INIS)

    Otsuka, N.; Semkova, V.; Simakov, S.P.; Zerkin, V.

    2011-01-01

    Dr Simakov of Nuclear Data Services Unit in the Nuclear Data Section (NDS) gave a brief overview of the data compilation and evaluation activities in the nuclear data community: experimental nuclear reaction data (EXFOR, http://www-nds.iaea.org/exfor/) and evaluated nuclear reaction data (ENDF, http://www-nds.iaea.org/endf). The International Network of Nuclear Reaction Data Centres (NRDC) coordinated by NDS includes 14 Centres in 8 Countries (China, Hungary, India, Japan, Korea, Russian, Ukraine, USA) and 2 International Organizations (NEA, IAEA). It had the first meeting of four core centres (Brookhaven, Saclay, Obninsk, Vienna) in 1966 and the EXFOR was adopted as an official data exchange format. In 2000, IAEA implemented the EXFOR database as a relational multiform database and the EXFOR is a trusted, increasing and living database with 19100 experimental works (as of September 2011) and 141600 data tables. The EXFOR provides a compilation control system for selection of articles and compilation of data and the NRDC home page provides manuals, documents and codes. The nuclear data can be retrieved by the web-retrieval system or distributed on a DVD on request. The EXFOR data play a critical role in the development of evaluated nuclear reaction data. There are several major general purpose libraries: ENDF (US), CENDL (China), JEFF (EU), JENDL (Japan) and RUSFOND (Russia). In addition, there are special libraries for particular applications: EAF (European Activation File), FENDL (Fusion Evaluated Nuclear Data Library for ITER neutronics), IBANDL (Ion Beam Analysis Nuclear Data Library for surface analysis of solids), IRDF, DXS (Dosimetry, radiation damage and gas production data) and Medical portal. Dr V. Zerkin of NDS demonstrated the data retrieval from the EXFOR database and the ENDF library.

  17. Experimental (Network) and Evaluated Nuclear Reaction Data at NDS

    Energy Technology Data Exchange (ETDEWEB)

    Otsuka, N; Semkova, V; Simakov, S P; Zerkin, V [Nuclear Data Services Unit, Nuclear Data Section, IAEA, Vienna (Austria)

    2011-11-15

    Dr Simakov of Nuclear Data Services Unit in the Nuclear Data Section (NDS) gave a brief overview of the data compilation and evaluation activities in the nuclear data community: experimental nuclear reaction data (EXFOR, http://www-nds.iaea.org/exfor/) and evaluated nuclear reaction data (ENDF, http://www-nds.iaea.org/endf). The International Network of Nuclear Reaction Data Centres (NRDC) coordinated by NDS includes 14 Centres in 8 Countries (China, Hungary, India, Japan, Korea, Russian, Ukraine, USA) and 2 International Organizations (NEA, IAEA). It had the first meeting of four core centres (Brookhaven, Saclay, Obninsk, Vienna) in 1966 and the EXFOR was adopted as an official data exchange format. In 2000, IAEA implemented the EXFOR database as a relational multiform database and the EXFOR is a trusted, increasing and living database with 19100 experimental works (as of September 2011) and 141600 data tables. The EXFOR provides a compilation control system for selection of articles and compilation of data and the NRDC home page provides manuals, documents and codes. The nuclear data can be retrieved by the web-retrieval system or distributed on a DVD on request. The EXFOR data play a critical role in the development of evaluated nuclear reaction data. There are several major general purpose libraries: ENDF (US), CENDL (China), JEFF (EU), JENDL (Japan) and RUSFOND (Russia). In addition, there are special libraries for particular applications: EAF (European Activation File), FENDL (Fusion Evaluated Nuclear Data Library for ITER neutronics), IBANDL (Ion Beam Analysis Nuclear Data Library for surface analysis of solids), IRDF, DXS (Dosimetry, radiation damage and gas production data) and Medical portal. Dr V. Zerkin of NDS demonstrated the data retrieval from the EXFOR database and the ENDF library.

  18. Actions concerning nuclear power plant life evaluation

    International Nuclear Information System (INIS)

    Chocron, M.; Fabbri, S.; Mizrahi, R.; Savino, E.J.; Versaci, R.A.

    1998-01-01

    One of the main activities to be undertaken by CNEA will be to provide technological assistance to NASA in problems concerning NPP operation. Works on life extensions of NPP are included in these activities. To fulfill these requirements the Atomic Energy National Commission (CNEA) has constituted a technical committee for Nuclear Power Plants Support (CAPCEN). CAPCEN should be the knowledge reservoir of those issues concerning the performance, safety and life extension of Nuclear Power Plants. One of CAPCEN's most important activities is to promote research work connected with such issues. The main technical areas are: Pressure Vessel and Piping, Heat Exchanges and Fuel Channels and Reactor Inner Components. Efforts are focused on the identification of the main components susceptible of ageing, the study of their ageing mechanisms, the follow-up of their behaviour during operation, and the measures taken to extend their life. (author)

  19. Methodology for Evaluating Safety System Operability using Virtual Parameter Network

    International Nuclear Information System (INIS)

    Park, Sukyoung; Heo, Gyunyoung; Kim, Jung Taek; Kim, Tae Wan

    2014-01-01

    KAERI (Korea Atomic Energy Research Institute) and UTK (University of Tennessee Knoxville) are working on the I-NERI project to suggest complement of this problem. This research propose the methodology which provide the alternative signal in case of unable guaranteed reliability of some instrumentation with KAERI. Proposed methodology is assumed that several instrumentations are working normally under the power supply condition because we do not consider the instrumentation survivability itself. Thus, concept of the Virtual Parameter Network (VPN) is used to identify the associations between plant parameters. This paper is extended version of the paper which was submitted last KNS meeting by changing the methodology and adding the result of the case study. In previous research, we used Artificial Neural Network (ANN) inferential technique for estimation model but every time this model showed different estimate value due to random bias each time. Therefore Auto-Associative Kernel Regression (AAKR) model which have same number of inputs and outputs is used to estimate. Also the importance measures in the previous method depend on estimation model but importance measure of improved method independent on estimation model. Also importance index of previous method depended on estimation model but importance index of improved method is independent on estimation model. In this study, we proposed the methodology to identify the internal state of power plant when severe accident happens also it has been validated through case study. SBLOCA which has large contribution to severe accident is considered as initiating event and relationship amongst parameter has been identified. VPN has ability to identify that which parameter has to be observed and which parameter can be alternative to the missing parameter when some instruments are failed in severe accident. In this study we have identified through results that commonly number 2, 3, 4 parameter has high connectivity while

  20. Methodology for Evaluating Safety System Operability using Virtual Parameter Network

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sukyoung; Heo, Gyunyoung [Kyung Hee Univ., Yongin (Korea, Republic of); Kim, Jung Taek [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Tae Wan [Kepco International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-05-15

    KAERI (Korea Atomic Energy Research Institute) and UTK (University of Tennessee Knoxville) are working on the I-NERI project to suggest complement of this problem. This research propose the methodology which provide the alternative signal in case of unable guaranteed reliability of some instrumentation with KAERI. Proposed methodology is assumed that several instrumentations are working normally under the power supply condition because we do not consider the instrumentation survivability itself. Thus, concept of the Virtual Parameter Network (VPN) is used to identify the associations between plant parameters. This paper is extended version of the paper which was submitted last KNS meeting by changing the methodology and adding the result of the case study. In previous research, we used Artificial Neural Network (ANN) inferential technique for estimation model but every time this model showed different estimate value due to random bias each time. Therefore Auto-Associative Kernel Regression (AAKR) model which have same number of inputs and outputs is used to estimate. Also the importance measures in the previous method depend on estimation model but importance measure of improved method independent on estimation model. Also importance index of previous method depended on estimation model but importance index of improved method is independent on estimation model. In this study, we proposed the methodology to identify the internal state of power plant when severe accident happens also it has been validated through case study. SBLOCA which has large contribution to severe accident is considered as initiating event and relationship amongst parameter has been identified. VPN has ability to identify that which parameter has to be observed and which parameter can be alternative to the missing parameter when some instruments are failed in severe accident. In this study we have identified through results that commonly number 2, 3, 4 parameter has high connectivity while

  1. Evaluation of nuclear data for neutron dosimetry

    International Nuclear Information System (INIS)

    Tardelli, Tiago Cardoso

    2013-01-01

    Absorbed dose and Effective dose are usually calculated using radiation transport computer codes. The quality of the calculations of absorbed dose depends on nuclear data utilized, however, there are rare information about the differences in dose caused by the use of different libraries. The objective of this study is to compare dose values obtained using different nuclear data libraries due to external source of neutrons in the energy range from 10-11 to 20 MeV. The nuclear data libraries used are: JENDL 4.0, JEFF 3.3.1 and ENDF/B.VII. Dose calculations were carried out with the MCNPX code considering the anthropomorphic ICRP 110 model. The differences in the absorbed dose values using JEFF 3.3.1 and ENDF/B.VII libraries are small, around 1%, but the results obtained with JENDL 4.0 presented differences up to 85% compared to ENDF and JEFF results. Differences in effective dose values are around 1.5% between ENDF and JEFF and 11% between ENDF/B.VII and JENDL 4.0. (author)

  2. The Derivation of Evaluation Criteria of Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Kim, S. K.; Ko, W. I.

    2013-01-01

    This study suggests the evaluation criteria and evaluation indicators derived using a factor analysis. As a result of a factor analysis, 5 evaluation criteria (safety (technological feature), environmental impact, economic feasibility, sociality, institution) and 24 evaluation indicators were selected. Particularly, the level of legislation for the management of radioactive waste, the level of establishment of safety standards of the country, and the level of application of international safety standards were analyzed to be qualitative evaluation indicators that should be considered in the aspect of the institution. The purpose of an analysis on diverse nuclear fuel cycles is to select the optimum nuclear fuel cycle suitable for the environment of one's own country. Accordingly, diverse evaluation criteria and evaluation indicators are necessary. In addition, individual evaluation criteria can be explained with various evaluation indicators. For example, the evaluation criteria for economic feasibility can be explained with evaluation indicators such as the unit cost or total cost. However, if too many evaluation indicators are included in one evaluation criterion, the evaluation is not easy, and if too few evaluation indicators are established, the evaluation criteria cannot be explained sufficiently, and thus the evaluation can be distorted. Accordingly, not only should the evaluation indicators be composed of an appropriate number of units, but they should also not be overlapped, and ambiguous evaluation indicators should be dropped out and necessary evaluation indicators must be included

  3. Relative evaluation on decommissioning accident scenarios of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, Kwan-Seong; Choi, Byung-Seon; Moon, Jei-Kwon; Hyun, Dong-Jun; Kim, Geun-Ho; Kim, Tae-Hyoung; Jo, Kyung-Hwa; Seo, Jae-Seok; Jeong, Seong-Young; Lee, Jung-Jun

    2012-01-01

    Highlights: ► This paper suggests relative importance on accident scenarios during decommissioning of nuclear facilities. ► The importance of scenarios can be performed by using AHP and Sugeno fuzzy method. ► The AHP and Sugeno fuzzy method guarantee reliability of the importance evaluation. -- Abstract: This paper suggests the evaluation method of relative importance on accident scenarios during decommissioning of nuclear facilities. The evaluation method consists of AHP method and Sugeno fuzzy integral method. This method will guarantee the reliability of relative importance evaluation for decommissioning accident scenarios.

  4. Large scale Bayesian nuclear data evaluation with consistent model defects

    International Nuclear Information System (INIS)

    Schnabel, G

    2015-01-01

    The aim of nuclear data evaluation is the reliable determination of cross sections and related quantities of the atomic nuclei. To this end, evaluation methods are applied which combine the information of experiments with the results of model calculations. The evaluated observables with their associated uncertainties and correlations are assembled into data sets, which are required for the development of novel nuclear facilities, such as fusion reactors for energy supply, and accelerator driven systems for nuclear waste incineration. The efficiency and safety of such future facilities is dependent on the quality of these data sets and thus also on the reliability of the applied evaluation methods. This work investigated the performance of the majority of available evaluation methods in two scenarios. The study indicated the importance of an essential component in these methods, which is the frequently ignored deficiency of nuclear models. Usually, nuclear models are based on approximations and thus their predictions may deviate from reliable experimental data. As demonstrated in this thesis, the neglect of this possibility in evaluation methods can lead to estimates of observables which are inconsistent with experimental data. Due to this finding, an extension of Bayesian evaluation methods is proposed to take into account the deficiency of the nuclear models. The deficiency is modeled as a random function in terms of a Gaussian process and combined with the model prediction. This novel formulation conserves sum rules and allows to explicitly estimate the magnitude of model deficiency. Both features are missing in available evaluation methods so far. Furthermore, two improvements of existing methods have been developed in the course of this thesis. The first improvement concerns methods relying on Monte Carlo sampling. A Metropolis-Hastings scheme with a specific proposal distribution is suggested, which proved to be more efficient in the studied scenarios than the

  5. Sonographic Evaluation of Renal Parameters in Individuals with ...

    African Journals Online (AJOL)

    2018-05-22

    May 22, 2018 ... sonographic parameters can be used to indirectly assess renal function or status. Ultrasound is an ... Hypertension seems to have more effect in the renal cortex than the medulla. ..... due to cost and use of ionizing radiation.

  6. SEMPaC - an expert system prototype associated with safety parameter display system of a nuclear power plant

    International Nuclear Information System (INIS)

    Hirama, K.

    1989-01-01

    This work presents SEMPaC, an expert system prototype: it provides means to support diagnosis and to make decisions during abnormal transients that cause the trip of nuclear power plant. The system operation is associated with Safety Parameter Display System - SPDS that was recommended by U. S. Nuclear Regulatory Commission (NRC) after the Three-Mile Island (TMI) accident analysis. (author)

  7. Evaluation of Injection Molding Process Parameters for Manufacturing Polyethylene Terephthalate

    Directory of Open Access Journals (Sweden)

    Marwah O.M.F.

    2017-01-01

    Full Text Available Quality control is an important aspect in manufacturing process. The quality of product in injection moulding is influenced by injection moulding process parameter. In this study, the effect of injection moulding parameter on defects quantity of PET preform was investigated. Optimizing the parameter of injection moulding process is critical to enhance productivity where parameters must operate at an optimum level for an acceptable performance. Design of Experiment (DOE by factorial design approach was used to find an optimum parameter setting and reduce the defects. In this case study, Minitab 17 software was used to analyses the data. The selected input parameters were mould hot runner temperature, water cooling chiller temperature 1 and water cooling chiller temperature 2. Meanwhile, the output for the process was defects quantity of the preform. The relationship between input and output of the process was analyzed using regression method and Analysis of Variance (ANOVA. In order to interpolate the experiment data, mathematical modeling was used which consists of different types of regression equation. Next, from the model, 95% confidence level (p-value was considered and the significant parameter was figured out. This study involved a collaboration with a preform injection moulding company which was Nilai Legasi Plastik Sdn Bhd. The collaboration enabled the researchers to collect the data and also help the company to improve the quality of its production. The results of the study showed that the optimum parameter setting that could reduce the defect quantity of preform was MHR= 88°C, CT1= 24°C and CT2= 27°C. The comparison defect quantity analysis between current companies setting with the optimum setting showed improvement by 21% reduction of defect quantity at the optimum setting. Finally, from the optimization plot, the validation error between the prediction value and experiment was 1.72%. The result proved that quality of products

  8. Evaluation of specific tritium transfer parameters in equilibrium conditions for Cernavoda area

    International Nuclear Information System (INIS)

    Paunescu, N.; Galeriu, D.; Mocanu, N.; Margineanu, R.

    1998-01-01

    In Romania, a CANDU nuclear power plant with five reactors of 600 MWe is under construction. The first unit reached its criticality on April 1996 and became operational at full power on December 1996. The nuclear power plant is placed in Cernavoda area, in the S-E of Romania, between the Danube River and the Danube-Black Sea Canal. The prevalent local climate is continental and agricultural activity in the neighbourhood of the nuclear power plant is of intensive type. The routine atmospheric tritium release from the 3 GWe nuclear power plant is expected to be about 460 TBq/year and the aqueous release is expected to be 350 TBq/year. The aim of this study was to evaluate the environmental tritium reference level before commissioning the nuclear power plant. Representative samples for Cernavoda area were analysed: air humidity; water from Danube River, Danube-Black Sea Canal, lakes; drinking and ground water, rain (snow) water; soil at different depths; tissue free water tritium in vegetal and animal foodstuff relevant for human diet: cereals (wheat, maize, barley), vegetables (potato, tomato, cabbage, onion, bean), fruits, grapes, wine and milk; organically bound tritium in wheat and maize grains. The equipment and methods used were: Liquid scintillation analyzer of type TRICARB 1900 TR; scintillation cocktails of Instagel and Pico Fluor LLT type; sampling system for trapping the atmospheric tritium on molecular sieves; furnace; vacuum line and freeze trap (-60 deg. C); equipment for simple, fractionating and azeotropic distillation. The background level of tritium concentration was determined in environmental samples in Cernavoda area, in preoperational stage of nuclear power plant. The mean values determined during 1994-early 1996 are : (7.4±5.5) Bq/L in air humidity, (3.1±1.0) Bq/L in water, (3.53±0.4) Bq/L in tissue water from vegetable and (4.9±1.7) Bq/L in tissue water from cereals (grains). The values of tritium concentration in air, water, soil and

  9. Tensor Fermi liquid parameters in nuclear matter from chiral effective field theory

    Science.gov (United States)

    Holt, J. W.; Kaiser, N.; Whitehead, T. R.

    2018-05-01

    We compute from chiral two- and three-body forces the complete quasiparticle interaction in symmetric nuclear matter up to twice nuclear matter saturation density. Second-order perturbative contributions that account for Pauli blocking and medium polarization are included, allowing for an exploration of the full set of central and noncentral operator structures permitted by symmetries and the long-wavelength limit. At the Hartree-Fock level, the next-to-next-to-leading order three-nucleon force contributes to all noncentral interactions, and their strengths grow approximately linearly with the nucleon density up to that of saturated nuclear matter. Three-body forces are shown to enhance the already strong proton-neutron effective tensor interaction, while the corresponding like-particle tensor force remains small. We also find a large isovector cross-vector interaction but small center-of-mass tensor interactions in the isoscalar and isovector channels. The convergence of the expansion of the noncentral quasiparticle interaction in Landau parameters and Legendre polynomials is studied in detail.

  10. Modern Nuclear Data Evaluation with the TALYS Code System

    Science.gov (United States)

    Koning, A. J.; Rochman, D.

    2012-12-01

    This paper presents a general overview of nuclear data evaluation and its applications as developed at NRG, Petten. Based on concepts such as robustness, reproducibility and automation, modern calculation tools are exploited to produce original nuclear data libraries that meet the current demands on quality and completeness. This requires a system which comprises differential measurements, theory development, nuclear model codes, resonance analysis, evaluation, ENDF formatting, data processing and integral validation in one integrated approach. Software, built around the TALYS code, will be presented in which all these essential nuclear data components are seamlessly integrated. Besides the quality of the basic data and its extensive format testing, a second goal lies in the diversity of processing for different type of users. The implications of this scheme are unprecedented. The most important are: 1. Complete ENDF-6 nuclear data files, in the form of the TENDL library, including covariance matrices, for many isotopes, particles, energies, reaction channels and derived quantities. All isotopic data files are mutually consistent and are supposed to rival those of the major world libraries. 2. More exact uncertainty propagation from basic nuclear physics to applied (reactor) calculations based on a Monte Carlo approach: "Total" Monte Carlo (TMC), using random nuclear data libraries. 3. Automatic optimization in the form of systematic feedback from integral measurements back to the basic data. This method of work also opens a new way of approaching the analysis of nuclear applications, with consequences in both applied nuclear physics and safety of nuclear installations, and several examples are given here. This applied experience and feedback is integrated in a final step to improve the quality of the nuclear data, to change the users vision and finally to orchestrate their integration into simulation codes.

  11. Modern Nuclear Data Evaluation with the TALYS Code System

    International Nuclear Information System (INIS)

    Koning, A.J.; Rochman, D.

    2012-01-01

    This paper presents a general overview of nuclear data evaluation and its applications as developed at NRG, Petten. Based on concepts such as robustness, reproducibility and automation, modern calculation tools are exploited to produce original nuclear data libraries that meet the current demands on quality and completeness. This requires a system which comprises differential measurements, theory development, nuclear model codes, resonance analysis, evaluation, ENDF formatting, data processing and integral validation in one integrated approach. Software, built around the TALYS code, will be presented in which all these essential nuclear data components are seamlessly integrated. Besides the quality of the basic data and its extensive format testing, a second goal lies in the diversity of processing for different type of users. The implications of this scheme are unprecedented. The most important are: 1. Complete ENDF-6 nuclear data files, in the form of the TENDL library, including covariance matrices, for many isotopes, particles, energies, reaction channels and derived quantities. All isotopic data files are mutually consistent and are supposed to rival those of the major world libraries. 2. More exact uncertainty propagation from basic nuclear physics to applied (reactor) calculations based on a Monte Carlo approach: “Total” Monte Carlo (TMC), using random nuclear data libraries. 3. Automatic optimization in the form of systematic feedback from integral measurements back to the basic data. This method of work also opens a new way of approaching the analysis of nuclear applications, with consequences in both applied nuclear physics and safety of nuclear installations, and several examples are given here. This applied experience and feedback is integrated in a final step to improve the quality of the nuclear data, to change the users vision and finally to orchestrate their integration into simulation codes.

  12. Two statistics for evaluating parameter identifiability and error reduction

    Science.gov (United States)

    Doherty, John; Hunt, Randall J.

    2009-01-01

    Two statistics are presented that can be used to rank input parameters utilized by a model in terms of their relative identifiability based on a given or possible future calibration dataset. Identifiability is defined here as the capability of model calibration to constrain parameters used by a model. Both statistics require that the sensitivity of each model parameter be calculated for each model output for which there are actual or presumed field measurements. Singular value decomposition (SVD) of the weighted sensitivity matrix is then undertaken to quantify the relation between the parameters and observations that, in turn, allows selection of calibration solution and null spaces spanned by unit orthogonal vectors. The first statistic presented, "parameter identifiability", is quantitatively defined as the direction cosine between a parameter and its projection onto the calibration solution space. This varies between zero and one, with zero indicating complete non-identifiability and one indicating complete identifiability. The second statistic, "relative error reduction", indicates the extent to which the calibration process reduces error in estimation of a parameter from its pre-calibration level where its value must be assigned purely on the basis of prior expert knowledge. This is more sophisticated than identifiability, in that it takes greater account of the noise associated with the calibration dataset. Like identifiability, it has a maximum value of one (which can only be achieved if there is no measurement noise). Conceptually it can fall to zero; and even below zero if a calibration problem is poorly posed. An example, based on a coupled groundwater/surface-water model, is included that demonstrates the utility of the statistics. ?? 2009 Elsevier B.V.

  13. Nuclear safety. How is it evaluated?

    International Nuclear Information System (INIS)

    Andersson, Kjell; Andersson, Johan; Carlsson, Lennart; Olsson, Richard; Ericsson, A.M.; Gunsell, L.; Wene, C.O.

    1996-09-01

    A working group with representatives for the three subject areas reactor safety, disposal of spent fuels and transport of radioactive materials has performed a project aiming to clarify similarities and differences of the three areas concerning methods for safety analysis, criteria, risks etc; and to develop contacts between experts in the areas in order to facilitate transfer of methods. Some of the more precise objectives were: To identify common problems that could be solved jointly, to discuss prospects for a 'meta-method' that can support safety analysis in the entire field of nuclear safety, and to discuss possibilities for a homogeneous attitude towards risk management

  14. ENSL and CDRL: Evaluated nuclear structure libraries

    International Nuclear Information System (INIS)

    Howerton, R.J.

    1981-01-01

    Two files of nuclear structure data derived largely from the seventh edition of the Table of Isotopes are described. The files are computer oriented, and have been constructed to so that every decay can be traced either to an eventual ground state of to a positive flag that indicates nothing is known about further decay. The ENSL file contains level schemes derived from decay data, and the CDRL file contains the level schemes derived from particle-induced reaction data that have been merged into the ENSL file. (author)

  15. Nuclear safety evaluation of the VVER 440, Type 213

    International Nuclear Information System (INIS)

    Urbancik, L.

    1997-01-01

    The supervisory activities of the State Office for Nuclear Safety at the Dukovany nuclear power plant are described. No event resulting in an inpermissible radioactivity leak into the environment occurred at the plant in 1996. From among the 76 failures and events having occurred, only 4 were classified as level 1 on the International Nuclear Event Scale. Changes in the technology of radioactive waste bituminization were proposed. The Interim Spent Fuel Storage Facility at the Dukovany site was in test operation in 1996. Selected physical parameters of this facility were monitored. Seven international transports of spent fuel were accomplished in 1996. The dose rates in the surroundings of the Dukovany plant are monitored constantly by a teledosimetric system operated by the nuclear power plant. Periodical sampling and radionuclide activity measurements in the environment are also performed. (M.D.)

  16. Initiatives in training program evaluation outside the nuclear utility industry

    International Nuclear Information System (INIS)

    Allen, C.J.

    1987-01-01

    Training literature is reviewed, and program evaluative practices outside the nuclear utility industry are reported. The findings indicate some innovations in philosophy and practice and program evaluation, although not necessarily in the context of evaluation as a route to assessing the impact of training. Program evaluation is described in the context of the impact of training, suggesting continued efforts to accept a multivariate concept of individual and organizational performance

  17. Nuclear data evaluation methodology including estimates of covariances

    Directory of Open Access Journals (Sweden)

    Smith D.L.

    2010-10-01

    Full Text Available Evaluated nuclear data rather than raw experimental and theoretical information are employed in nuclear applications such as the design of nuclear energy systems. Therefore, the process by which such information is produced and ultimately used is of critical interest to the nuclear science community. This paper provides an overview of various contemporary methods employed to generate evaluated cross sections and related physical quantities such as particle emission angular distributions and energy spectra. The emphasis here is on data associated with neutron induced reaction processes, with consideration of the uncertainties in these data, and on the more recent evaluation methods, e.g., those that are based on stochastic (Monte Carlo techniques. There is no unique way to perform such evaluations, nor are nuclear data evaluators united in their opinions as to which methods are superior to the others in various circumstances. In some cases it is not critical which approaches are used as long as there is consistency and proper use is made of the available physical information. However, in other instances there are definite advantages to using particular methods as opposed to other options. Some of these distinctions are discussed in this paper and suggestions are offered regarding fruitful areas for future research in the development of evaluation methodology.

  18. Methodologies for evaluating the proliferation resistance of nuclear fuel cycles

    International Nuclear Information System (INIS)

    Shiotani, Hiroki; Hori, Kei-ichiro; Takeda, Hiroshi

    2001-01-01

    The Japan Nuclear Cycle Development Institute (JNC) believes that the development of future nuclear fuel cycle technology should be conducted with careful consideration given to non-proliferation. JNC is studying methodologies for evaluating proliferation resistance of nuclear fuel cycle technologies. However, it is difficult to establish the methodology for evaluating proliferation resistance since the results greatly depend on the assumption for the evaluation and the surrounding conditions. This study grouped factors of proliferation resistance into categories through reviewing past studies and studied the relationships between the factors. Then, this study tried to find vulnerable nuclear material (plutonium) in some FBR fuel cycles from the proliferation perspective, and calculated the time it takes to convert the materials from various nuclear fuel cycles into pure plutonium metal under some assumptions. The result showed that it would take a long time to convert the nuclear materials from the FBR fuel cycles without plutonium separation. While it is a preliminary attempt to evaluate a technical factor of proliferation resistance as the basis of the institutional proliferation resistance, the JNC hopes that it will contribute to future discussions in this area. (author)

  19. Technical evaluation of bids for nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    In continuation of its efforts to provide comprehensive and impartial guidance to Member States facing the need to introduce nuclear power, the International Atomic Energy Agency is issuing this guidebook as part of a series of guidebooks and codes of practice and, in particular, as a necessary supplement to 'Economic Evaluation of Bids for Nuclear Power Plants: A Guidebook', published by the IAEA in 1976 as Technical Reports Series No.175. The present publication is intended for project managers and senior engineers of electric utilities who are concerned with the evaluation of bids for a nuclear power project. It assumes that the reader has a good knowledge of the technical characteristics of nuclear power plants and of nuclear power project implementation. Its purpose is to provide the information necessary to organize, guide and supervise the technical evaluation of bids for a nuclear power project. It goes without saying that the technical staff carrying out the evaluation must have prior technical experience which cannot be provided by a guidebook

  20. Instructional skills evaluation in nuclear industry training

    International Nuclear Information System (INIS)

    Mazour, T.J.; Ball, F.M.

    1985-11-01

    This report provides information to nuclear power plant training managers and their staffs concerning the job performance requirements of instructional personnel to implement prformance-based training programs (also referred to as the Systems Approach Training). The information presented in this report is a compilation of information and lessons learned in the nuclear power industry and in other industries using performance-based training programs. The job performance requirements in this report are presented as instructional skills objectives. The process used to develop the instructional skills objectives is described. Each objective includes an Instructional Skills Statement describing the behavior that is expected and an Instructional Skills Standard describing the skills/knowledge that the individual should possess in order to have achieved mastery. The instructional skills objectives are organized according to the essential elements of the Systems Approach to Training and are cross-referenced to three categories of instructional personnel: developers of instruction, instructors, and instructional managers/supervisors. Use of the instructional skills objectives is demonstrated for reviewing instructional staff training and qualification programs, developing criterion-tests, and reviewing the performance and work products of individual staff members. 22 refs

  1. Evaluation of the status of national nuclear infrastructure development

    International Nuclear Information System (INIS)

    2008-01-01

    An appropriate infrastructure is essential for the safe, reliable and peaceful use of nuclear power. The IAEA was encouraged to assess ways to meet infrastructure needs and to provide guidance to Member States considering the introduction of nuclear power. All of these countries face the challenge of building the necessary nuclear infrastructure for the first nuclear power plant. The IAEA is responding to this demand through increased technical assistance, missions and workshops, and with new and updated technical publications. A holistic view of the infrastructure for nuclear power was published in Considerations to Launch a Nuclear Power Programme (GOV/INF/2007), targeted mainly at policy makers. Milestones in the Development of a National Infrastructure for Nuclear Power, an IAEA Nuclear Energy Series publication (No. NG-G-3.1) issued in 2007, provided more detailed guidance on the three phases of development outlined in Considerations to Launch a Nuclear Power Programme. It describes the sequential development through the three phases for each of 19 infrastructure issues, ranging from a government's national position on nuclear power to the procurement of items and services for the first nuclear power plant. Member States requested additional guidance on determining how to assess the progress of their infrastructure development for nuclear power programmes. This report was prepared in response to their request. It provides an evaluation approach for the status of national nuclear infrastructure development based upon the guidance presented in the Milestones publication mentioned above. The evaluation approach provides a comprehensive means to determine the status of the infrastructure conditions covering all of the 19 issues identified in the Milestones publication. This approach can be used by any interested Member State for self-evaluation in order to establish what additional work needs to be completed to develop the appropriate national infrastructure. In

  2. Evaluated nuclear data file ENDF/B-VI

    International Nuclear Information System (INIS)

    Dunford, C.L.

    1991-01-01

    For the past 25 years, the United States Department of Energy has sponsored a cooperative program among its laboratories, contractors and university research programs to produce an evaluated nuclear data library which would be application independent and universally accepted. The product of this cooperative activity is the ENDF/B evaluated nuclear data file. After approximately eight years of development, a new version of the data file, ENDF/B-VI has been released. The essential features of this evaluated data library are described in this paper. 7 refs

  3. Nuclear source term evaluation for launch accident environments

    Energy Technology Data Exchange (ETDEWEB)

    McCulloch, W.H.

    1996-05-01

    When United States space missions involve launching vehicles carrying significant quantities of nuclear material, US law requires that prior to launch the mission be approved by the Office of the President. This approval is to be based on an evaluation of the nuclear safety risks associated with the mission and the projected benefits. To assist in the technical evaluation of risks for each mission, an Interagency Nuclear Safety Review Panel (INSRP) is instituted to provide an independent assessment of the mission risks. INSRP`s assessment begins with a review of the safety analysis for the mission completed by the organization proposing the mission and documented in a Safety Analysis Report (SAR). In addition, INSRP may execute other analyses it deems necessary. Results are documented and passed to the decision maker in a Safety Evaluation Report (SER). The INSRP review and evaluation process has been described in some detail in a number of papers.

  4. Nuclear source term evaluation for launch accident environments

    International Nuclear Information System (INIS)

    McCulloch, W.H.

    1996-01-01

    When United States space missions involve launching vehicles carrying significant quantities of nuclear material, US law requires that prior to launch the mission be approved by the Office of the President. This approval is to be based on an evaluation of the nuclear safety risks associated with the mission and the projected benefits. To assist in the technical evaluation of risks for each mission, an Interagency Nuclear Safety Review Panel (INSRP) is instituted to provide an independent assessment of the mission risks. INSRP's assessment begins with a review of the safety analysis for the mission completed by the organization proposing the mission and documented in a Safety Analysis Report (SAR). In addition, INSRP may execute other analyses it deems necessary. Results are documented and passed to the decision maker in a Safety Evaluation Report (SER). The INSRP review and evaluation process has been described in some detail in a number of papers

  5. Bid Preparation and Evaluation for Nuclear Power Plant Project Management

    International Nuclear Information System (INIS)

    Mohd Idris Taib, Mohd Khairulezwan Abdul Manan and Nur Farizan Amadzun

    2011-01-01

    Bid preparation and evaluation is one of the main activities in Nuclear Power Plant Project management. International Atomic Energy Agency guide and Korean experience was studied for Malaysian requirement in realization of first Nuclear Power Plant. Several aspects shall be taken into consideration such as political scenario, financial capabilities, sitting, human resource, technologies, fuel supplies and decommissioning for long term exceeded hundred years. Bidding process and activities is proposed for our country requirement. The main activities included but unlimited to Bid Invitation Specification, Bid Evaluation Process, Technical Evaluation, Economic Bid Evaluation and Contracting. On the end of day, Malaysia need safe and reliable Nuclear Power Plant. Malaysian Economic Transformation Programme also get benefit from spin-off localization products and services as well as Technology Transfer Programme. (author)

  6. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Kim, Yun Jae; Choi, Jae Boong [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

    2002-03-15

    This project focuses on developing reliable life evaluation technology for nuclear power plant components, and is divided into two parts, development of a life evaluation system for nuclear pressure vessels and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered in this project: defect assessment method for steam generator tubes, development of fatigue monitoring system, assessment of corroded pipes, domestic round robin analysis for constructing P-T limit curve for RPV, development of probabilistic integrity assessment technique, effect of aging on strength of dissimilar welds, applicability of LBB to cast stainless steel, and development of probabilistic piping fracture mechanics.

  7. Nuclear power plant personnel training and its evaluation. A guidebook

    International Nuclear Information System (INIS)

    1996-01-01

    The Guidebook will prove especially useful for, and is addressed primarily to: nuclear power operating organizations establishing or upgrading their NPP personnel training systems; regulatory personnel responsible for setting requirements and/or evaluating NPP personnel training; and organizations (within or outside the operating organization) responsible for the development, implementation and evaluation of training programmes for NPP personnel. Figs, tabs

  8. Review Article : Utilization of Environmental Radiochemistry Techniques for Selection and Evaluation of Nuclear Facility Sites

    International Nuclear Information System (INIS)

    Atta, E.R.; Madbouly, A.M.; Zakaria, Kh.M.

    2016-01-01

    This research review puts necessary considerations on the available environmental radiochemistry techniques for selection and evaluation of a nuclear facility sites.The main bjective in site evaluation for nuclear facilities in terms of nuclear safety is to protect the site workers, the public and the environment from the effects of ionizing radiation release from nuclear facilities due to accidents. The extreme sensitivity and speed of radiochemical methods make their applications of considerable importance in several fields and they have found many uses. Information about the existed radioactivity in the different nuclear facilities is an essential requirement for their environmental assessment. It is necessary to estimate the various radioactivity levels in the environment through qualitative and quantitative analytical techniques and to assess the potential effects of the nuclear facility in the region by considering the characteristics of sites.The siting and site evaluation requirements are discussed. Emphasis was given to types of radiochemical techniques used for characterization of the site parameters which determine the potential hazards of the site on the facility and the facility on the site. Emphasis has been also given to the quantitative and qualitative analysis of naturally occurring radionuclides for monitoring and control .There are some techniques employed such as radioactive tracer technique, liquid scintillation technique, gamma spectrometry technique, neutron activation analysis technique, fluorimetric technique and isotope hydrology technique.

  9. Evaluation of the growth parameters of six commercial crossbred pig ...

    African Journals Online (AJOL)

    To test whether animals grown under ideal temperature conditions would have different growth parameters to animals grown in more conventional housing, 60 Large White x Landrace male pigs from three genotypes were housed in six temperature-controlled chambers. The results were compared with data from a similar ...

  10. Evaluation of Neonatal Hemolytic Jaundice: Clinical and Laboratory Parameters

    Directory of Open Access Journals (Sweden)

    Anet Papazovska Cherepnalkovski

    2015-12-01

    CONCLUSIONS: The laboratory profile in ABO/Rh isoimmunisation cases depicts hemolytic mechanism of jaundice. These cases carry a significant risk for early and severe hyperbilirubinemia and are eligible for neurodevelopmental follow-up. Hematological parameters and blood grouping are simple diagnostic methods that assist the etiological diagnosis of neonatal hyperbilirubinemia.

  11. Evaluation of some handling and processing parameters for ...

    African Journals Online (AJOL)

    Biomass materials require reduction and densification for the purpose of handling and space requirements. Guinea corn (Sorghum bi-color) is a major source of biomass material in the tropic regions. The densification process involves some measurable parameters, namely: pressure, particles size and binder ratio. Guinea ...

  12. Evaluation of selected parameters of rat liver and kidney function ...

    African Journals Online (AJOL)

    The effects of administration of yohimbine, an aphrodisiac on some functional parameters of rat liver and kidney were investigated. White male albino rats weighing between 200-250g were grouped into two such that one group was orally administered with 14mg/kg body weight on daily basis for 15days while the control ...

  13. Evaluating the Aspect of Nuclear Material in Fuel Cycles

    Energy Technology Data Exchange (ETDEWEB)

    Takagi, Shunsuke; Pickett, Susan; Oda, Takuji; Choi, Jor-Shan; Kuno, Yusuke; Takana, Satoru [Department of Nuclear Engineering and Management, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8685 (Japan); Nagasaki, Shinya [Nuclear Professional School, The University of Tokyo (Japan)

    2009-06-15

    The increasing number of countries that wish to introduce nuclear power plants raises attention to proliferation resistance in nuclear power plants, and nuclear fuel cycle facilities. In order to achieve adequate proliferation resistance, it is important to evaluate it and to construct effective international institutional frameworks as well as technologies involving high level of proliferation resistance. Although some methods have been proposed for evaluation of the proliferation resistance, their validities have not been investigated in detail. In the present paper, therefore, we compare some of the proposed methodologies. It is essential to detect the abuse or diversion of nuclear material before the nuclear explosive device can be manufactured in order to prevent proliferation. The time needed for the detection of material primary depends on the safeguards that the country applies, and the time needed for fabrication mainly depends on the attributes of the nuclear material. Hence, we divided the proliferation resistance into two parts: the level of safeguards and the material. For examination of evaluation methods such as the one proposed by Charlton [1] or the figure of merit (FOM) [2], sensitivity analysis was performed on weighting factors and scenarios. The validity and characteristics of each method were discussed, focusing on the applicability of each method to the assessment of multi-national approaches such as GNEP. [1] W. S. Charlton, R. L. LeBouf, C. Gariazzo, D. G. Ford, C. Beard, S. Landeberger, M. Whitaker, 'Proliferation resistance assessment methodology for nuclear fuel cycles', Nuclear Technology, 157, 1 (2007). [2] C.G. Bathke et al, 'An assessment of the proliferation resistance of materials in advanced nuclear fuel cycles', 8. International Conference on Facility Operations (2008). (authors)

  14. Examination of State-Level Nuclear Security Evaluation Methods

    International Nuclear Information System (INIS)

    Kim, Chan Kim; Yim, Man-Sung

    2015-01-01

    An effective global system for nuclear materials security needs to cover all materials, employing international standards and best practices, to reduce risks by reducing weapons-usable nuclear material stocks and the number of locations where they are found. Such a system must also encourage states to accept peer reviews by outside experts in order to demonstrate that effective security is in place. It is thus critically important to perform state-level evaluation of nuclear security based on an integrative framework of risk assessment. Such evaluation provides a basis of measuring the level and progress of international effort to secure and control all nuclear materials. sensitivity test by differentiating weight factors of each of the indicators and categories will be performed in the future as well

  15. In-core program for on line measurements of neutron, photon and nuclear heating parameters inside Jules Horowitz MTR reactor

    International Nuclear Information System (INIS)

    Lyoussi, A.; Reynard-Carette, C.

    2014-01-01

    Accurate on-line measurements of key parameters inside experimental channels of Material Testing Reactor are necessary to dimension the irradiation devices and consequently to conduct smart experiments on fuels and materials under suitable conditions. In particular the quantification of nuclear heating, a relevant parameter to reach adapted thermal conditions, has to be improved. These works focus on an important collaborative program between CEA and Aix-Marseille University called INCORE (Instrumentation for Nuclear radiations and Calorimetry On-line in Reactor) dedicated to the development of a new measurement methodology to quantify both nuclear heating and accurate radiation flux levels (neutrons and photons). The methodology, which is based on experiments carried out under irradiation conditions with a multi-sensor device (ionization chamber, fission chamber, gamma thermometer, calorimeter, SPND, SPGD) as well as works performed out-of nuclear/radiative environment on a reference sensor used to measure nuclear heating (calorimeter), is presented (authors)

  16. Parameter Data on the Radiocesium Transfer to Korean Staple Food Crops Following a Nuclear Accident

    International Nuclear Information System (INIS)

    Choi, Yong-Ho; Lim, Kwang-Muk; Jun, In; Kim, Byung-Ho; Keum, Dong-Kwon

    2016-01-01

    In order to decide an optimum countermeasure against farmland contaminations following a severe NPP accident, it is necessary to have a reliable tool for predicting the concentrations of radiocesium in crop plants. For the estimation of radionuclide concentrations in crop plants, various transfer parameters, which quantify the radionuclide transfer from one compartment to the next, are used in general. Some amount of transfer parameter data has been produced at the Korea Atomic Energy Research Institute (KAERI) over the last 30 years. The present work was conducted to collate the KAERI data on radiocesium in staple food crops and to suggest effective ways of using them for assessing the environmental impact of a nuclear accident. The transfer parameter values of radiocesium for rice, Chinese cabbage and radish varied considerably with soils and times of its deposition. The proposed representative values were mostly based on a limited amount of data so they cannot be considered to have a high representativeness. Accordingly, they are intended for provisional use and a continuous improvement should be made. It is necessary to produce a sufficient amount of additional domestic data on the indirect pathway by conducting root-uptake experiments with as many types of soil as possible

  17. Parameter Data on the Radiocesium Transfer to Korean Staple Food Crops Following a Nuclear Accident

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yong-Ho; Lim, Kwang-Muk; Jun, In; Kim, Byung-Ho; Keum, Dong-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In order to decide an optimum countermeasure against farmland contaminations following a severe NPP accident, it is necessary to have a reliable tool for predicting the concentrations of radiocesium in crop plants. For the estimation of radionuclide concentrations in crop plants, various transfer parameters, which quantify the radionuclide transfer from one compartment to the next, are used in general. Some amount of transfer parameter data has been produced at the Korea Atomic Energy Research Institute (KAERI) over the last 30 years. The present work was conducted to collate the KAERI data on radiocesium in staple food crops and to suggest effective ways of using them for assessing the environmental impact of a nuclear accident. The transfer parameter values of radiocesium for rice, Chinese cabbage and radish varied considerably with soils and times of its deposition. The proposed representative values were mostly based on a limited amount of data so they cannot be considered to have a high representativeness. Accordingly, they are intended for provisional use and a continuous improvement should be made. It is necessary to produce a sufficient amount of additional domestic data on the indirect pathway by conducting root-uptake experiments with as many types of soil as possible.

  18. Determination of welding parameters for execution of weld overlayer on PWR nuclear reactor nozzles

    International Nuclear Information System (INIS)

    Ribeiro, Gabriela M.; Lima, Luciana I.; Quinan, Marco A.; Schvartzman, Monica M.

    2009-01-01

    In the PWR reactors, nickel based dissimilar welds have been presented susceptibilities the stress corrosion (S C). For the mitigation the problem a deposition of weld layers on the external surface of the nozzle is an alternative, viewing to provoke the compression of the region subjected to S C. This paper presents a preliminary study on the determination of welding parameters to obtain these welding overlayers. Welding depositions were performed on a test piece welded with nickel 182 alloy, simulating the conditions of a nozzle used in a PWR nuclear power plant. The welding process was the GTAW (Gas Tungsten Arc Welding), and a nickel 52 alloy as addition material. The overlayers were performed on the base metals, carbon steel an stainless steel, changing the welding parameters and verifying the the time of each weld filet. After that, the samples were micro structurally characterized. The macro structures and the microstructures obtained through optical microscopy and Vickers microhardness are presented. The preliminary results make evident the good weld quality. However, a small weld parameters influence used in the base material microstructure (carbon steel and stainless steel). The obtained results in this study will be used as reference in the construction of a mock up which will simulate all the conditions of a pressurizer nozzle of PWR reactor

  19. Software for MUF evaluating in item nuclear material accounting

    International Nuclear Information System (INIS)

    Wang Dong; Zhang Quanhu; He Bin; Wang Hua; Yang Daojun

    2009-01-01

    Nuclear material accounting is a key measure for nuclear safeguard. Software for MUF evaluation in item nuclear material accounting was worked out in this paper. It is composed of several models, including input model, data processing model, data inquiring model, data print model, system setting model etc. It could be used to check the variance of the measurement and estimate the confidence interval according to the MUF value. To insure security of the data multi-user management function was applied in the software. (authors)

  20. Validity evaluation of internal exposure in nuclear facility decommission

    International Nuclear Information System (INIS)

    Wang Xiaoli; Chen Dahua; You Zeyun

    2012-01-01

    During nuclear facility decommission under construction, it is very important for workers to wear respirator to avoid harm of Am aerosols. So the protection effect of respirator is very important. The protection effect of respirator was calculated and evaluated according to the data achieved from engineering practice. The result shows that the protection effect is better than target management value and the respirator is effective to protect workers from harm of Am aerosols. The respirator is applied to other nuclear facility decommission. (authors)

  1. The evaluation of site characteristics for Guangdong nuclear power plant

    International Nuclear Information System (INIS)

    Zhou Ruming; Wu Dizhong; Yan Zhongmin

    1987-01-01

    This paper gives an account of the features of the site of Guangdong Nuclear Power Plant (GNPP) in general and in particular evaluates the outstanding site characteristics related to nuclear safety and public health. It is composed of two parts: the first part describes the seismo-geologic conditions of the site and the other treats the atmospheric dispersion conditions. It also contains the discussion why the possibility of inhabitancy within 5 km from the exclusion ares boundary would not be affected. (author)

  2. JENDL-3. The Japanese evaluated nuclear data library

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1992-01-01

    This document summarizes the contents of JENDL-3.1, the Japanese evaluated data library for neutron nuclear data, released in 1989 and revised in Dec. 1990. It also summarizes the JENDL-3 fission-products cross-section data library released in 1990. The entire library or retrievals of selected materials are available on magnetic tape from the IAEA Nuclear Data Section free of charge. (author)

  3. Method discussion of the performance evaluation on nuclear plant cable

    International Nuclear Information System (INIS)

    Lu Yongfang; Zhong Weixia; Sun Jiansheng; Liu Jingping

    2014-01-01

    A stock cable, which is same as the nuclear plant cable in service, was treated by thermal aging. After that, the mechanical property, the flame retardant property, the anti-oxidation were measured, and relationships between them due to the thermal aging were established. By those analysis, evaluating the in-service cable performance in nuclear plant and calculating its remaining life. Furthermore, the feasibility of this method was disscussed. (authors)

  4. Exercises for radiological and nuclear emergency response. Planing - performance - evaluation

    International Nuclear Information System (INIS)

    Bayer, A.; Faleschini, J.; Goelling, K.; Stapel, R.; Strobl, C.

    2010-01-01

    The report of the study group emergency response seminar covers the following topics: (A) purpose of exercises and exercise culture: fundamentals and appliances for planning, performance and evaluation; (B) exercises in nuclear facilities; (C) exercises of national authorities and aid organizations on nuclear scenarios; exercises of national authorities and aid organizations on other radiological scenarios; (D) exercises in industrial plants, universities, medical facilities and medical services, and research institutes; (E) transnational exercises, international exercises; (F): exercises on public information.

  5. Application of extreme value distribution function in the determination of standard meteorological parameters for nuclear power plants

    International Nuclear Information System (INIS)

    Jiang Haimei; Liu Xinjian; Qiu Lin; Li Fengju

    2014-01-01

    Based on the meteorological data from weather stations around several domestic nuclear power plants, the statistical results of extreme minimum temperatures, minimum. central pressures of tropical cyclones and some other parameters are calculated using extreme value I distribution function (EV- I), generalized extreme value distribution function (GEV) and generalized Pareto distribution function (GP), respectively. The influence of different distribution functions and parameter solution methods on the statistical results of extreme values is investigated. Results indicate that generalized extreme value function has better applicability than the other two distribution functions in the determination of standard meteorological parameters for nuclear power plants. (authors)

  6. The use of tritiated water in evaluating animal production parameters

    International Nuclear Information System (INIS)

    Robertshaw, D.

    1988-01-01

    Tritiated water (TOH) provides a means of measuring a number of parameters of importance not only to the applied animal physiologist but to those involved in assessing animal productivity. For the examination of animal-environment interactions, TOH is an invaluable tool for assessing total body water, water turnover rate and hence water requirements of different types of animals kept under a variety of climatic and other conditions. It can also be useful for measuring water losses, e.g. through evaporation, and hence is a tool for assessing thermal stress. For animal productivity studies, TOH is useful for assessing such parameters as carcass composition, the intake of forages, supplements and milk. Each of these aspects is described as are the assumptions which have to be made when using TOH for the measurements concerned. (author). 11 refs, 1 tab

  7. Experimental evaluation of a modal parameter based system identification procedure

    Science.gov (United States)

    Yu, Minli; Feng, Ningsheng; Hahn, Eric J.

    2016-02-01

    Correct modelling of the foundation of a rotor bearing foundation system (RBFS) is an invaluable asset for the balancing and efficient running of turbomachinery. Numerical experiments have shown that a modal parameter based identification approach could be feasible for this purpose but there is a lack of experimental verification of the suitability of such a modal approach for even the simplest systems. In this paper the approach is tested on a simple experimental rig comprising a clamped horizontal bar with lumped masses. It is shown that apart from damping, the proposed approach can identify reasonably accurately the relevant modal parameters of the rig; and that the resulting equivalent system can predict reasonably well the frequency response of the rig. Hence, the proposed approach shows promise but further testing is required, since application to identifying the foundation of an RBFS involves the additional problem of accurately obtaining the force excitation from motion measurements.

  8. Nuclear criticality safety evaluation of large cylinder cleaning operations in X-705, Portsmouth Gaseous diffusion Plant

    International Nuclear Information System (INIS)

    Sheaffer, M.K.; Keeton, S.C.; Lutz, H.F.

    1995-06-01

    This report evaluates nuclear criticality safety for large cylinder cleaning operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current cleaning procedures and required hardware/equipment is presented, and documentation for large cylinder cleaning operations is identified and described. Control parameters, design features, administrative controls, and safety systems relevant to nuclear criticality are discussed individually, followed by an overall assessment based on the Double Contingency Principle. Recommendations for enhanced safety are suggested, and issues for increased efficiency are presented

  9. Nuclear energy and astrophysics applications of ENDF/B-VII.1 evaluated nuclear library

    International Nuclear Information System (INIS)

    Pritychenko, B.

    2012-01-01

    Recently released ENDF/B-VII.1 evaluated nuclear library contains the most up-to-date evaluated neutron cross section and covariance data. These data provide new opportunities for nuclear science and astrophysics application development. The improvements in neutron cross section evaluations and more extensive utilization of covariance files, by the Cross Section Evaluation Working Group (CSEWG) collaboration, allowed users to produce neutron thermal cross sections, Westcott factors, resonance integrals, Maxwellian-averaged cross sections and astrophysical reaction rates, and provide additional insights on the currently available neutron-induced reaction data. Nuclear reaction calculations using the ENDF/B-VII.1 library and current computer technologies will be discussed and new results will be presented

  10. Analysis of parameter uncertainties in the assessment of seismic risk for nuclear power plants

    International Nuclear Information System (INIS)

    Yucemen, S.M.

    1981-04-01

    Probabilistic and statistical methods are used to develop a procedure by which the seismic risk at a specific site can be systematically analyzed. The proposed probabilistic procedure provides a consisted method for the modelling, analysis and updating of uncertainties that are involved in the seismic risk analysis for nuclear power plants. Methods are proposed for including these uncertainties in the final value of calculated risks. Two specific case studies are presented in detail to illustrate the application of the probabilistic method of seismic risk evaluation and to investigate the sensitivity of results to different assumptions

  11. Evaluation of resonance parameters of Mo, Tc, Te, Ba, La, Ce, Pr, Nd, Pm, Sm and Eu isotopes for JENDL-2 fission product file

    International Nuclear Information System (INIS)

    Kikuchi, Yasuyuki; Togawa, Orihiko; Nakagawa, Tsuneo

    1986-03-01

    The resonance parameters of 39 fission product nuclides have been evaluated. The present work is a part of the evaluation of 100 fission product nuclei for JENDL-2 by Japanese Nuclear Data Committee. All the available experimental data were collected, stored in REPSTOR system and compared with one another. The evaluation was made on the basis of the experimental data. The precise description of the evaluation is given in this report. The presently evaluated resonance parameters are tabulated in Appendix with the experimental data. (author)

  12. Status of transactinium nuclear data in the Evaluated Nuclear Structure Data File

    International Nuclear Information System (INIS)

    Ewbank, W.B.

    1979-01-01

    The organization and program of the Nuclear Data Project are described. An Evaluated Nuclear Structure Data File (ENSDF) was designed to contain most of the data of nuclear structure physics. ENSDF includes adopted level information for all 1950 known nuclei, and detailed data for approximately 1500 decay schemes. File organization, management, and retrieval are reviewed. An international network of data evaluation centers has been organized to provide for a four-year cycle of ENSDF revisions. Standard retrieval and display programs can prepare various tables of specific data, which can serve as a good first approximation to a complete up-to-date compilation. Appendixes list, for A > 206, nuclear levels with lifetimes > or = 1 s, strong γ rays from radioisotopes (ordered by nuclide and energy), and strong α particle emissions (similarly ordered). 8 figures

  13. Evaluation of severe accident risks: Quantification of major input parameters

    International Nuclear Information System (INIS)

    Harper, F.T.; Breeding, R.J.; Brown, T.D.; Gregory, J.J.; Payne, A.C.; Gorham, E.D.; Amos, C.N.

    1990-12-01

    This report records part of the vast amount of information received during the expert judgment elicitation process that took place in support of the NUREG-1150 effort sponsored by the US Nuclear Regulatory Commission. The results of the In-Vessel Expert Panel are presented in this part of Volume 2 of NUREG/CR-4551. The In-Vessel Panel considered six issues: temperature-induced pressurized water reactor (PWR) hot leg or surge line failure before vessel breach; temperature-induced steam generator tube rupture (SGTR) before vessel breach; boiling water reactor (BWR) in-vessel hydrogen production; BWR bottom head failure; PWR in-vessel hydrogen generation; and PWR bottom head failure. 83 refs., 58 figs., 56 tabs

  14. Prospects for development of an innovative water-cooled nuclear reactor for supercritical parameters of coolant

    Science.gov (United States)

    Kalyakin, S. G.; Kirillov, P. L.; Baranaev, Yu. D.; Glebov, A. P.; Bogoslovskaya, G. P.; Nikitenko, M. P.; Makhin, V. M.; Churkin, A. N.

    2014-08-01

    The state of nuclear power engineering as of February 1, 2014 and the accomplished elaborations of a supercritical-pressure water-cooled reactor are briefly reviewed, and the prospects of this new project are discussed based on this review. The new project rests on the experience gained from the development and operation of stationary water-cooled reactor plants, including VVERs, PWRs, BWRs, and RBMKs (their combined service life totals more than 15 000 reactor-years), and long-term experience gained around the world with operation of thermal power plants the turbines of which are driven by steam with supercritical and ultrasupercritical parameters. The advantages of such reactor are pointed out together with the scientific-technical problems that need to be solved during further development of such installations. The knowledge gained for the last decade makes it possible to refine the concept and to commence the work on designing an experimental small-capacity reactor.

  15. Measures of the zero power nuclear reactor's kinetic parameters with application of noise analysis

    International Nuclear Information System (INIS)

    Martins, F.R.

    1992-01-01

    The purpose of this work was to establish an experimental technique based on noise analysis for measuring the ratio of kinetic parameters β/ Λ and the power of the Zero Power Nuclear Reactor IPEN-MB 01. A through study of the microscopic and macroscopic noise analysis techniques has been carried out. The Langevin technique and the point kinetic model were chosen to describe the stochastic phenomena that occur in the zero power reactor. Measurements have been made using two compensated ionization chambers localized in the water reflector at symmetric positions in order to minimize spatial effects on the neutron flux fluctuation. Power calibrations based on the low frequency plateau of the cross-power spectral density has also been carried out. (author)

  16. Nuclear irradiation parameters of beryllium under fusion, fission and IFMIF irradiation conditions

    International Nuclear Information System (INIS)

    Fischer, U.; Chen, Y.; Leichtle, D.; Simakov, S.; Moeslang, A.; Vladimirov, P.

    2004-01-01

    A computational analysis is presented of the nuclear irradiation parameters for Beryllium under irradiation in typical neutron environments of fission and fusion reactors, and of the presently designed intense fusion neutron source IFMIF. The analysis shows that dpa and Tritium production rates at fusion relevant levels can be achieved with existing high flux fission reactors while the achievable Helium production is too low. The resulting He-Tritium and He/dpa ratios do not meet typical fusion irradiation conditions. Irradiation simulations in the medium flux test modules of the IFMIF neutron source facility were shown to be more suitable to match fusion typical irradiation conditions. To achieve sufficiently high production rates it is suggested to remove the creep-fatigue testing machine together with the W spectra shifter plate and move the tritium release module upstream towards the high flux test module. (author)

  17. Development and evaluation of first responder equipment for nuclear forensics

    International Nuclear Information System (INIS)

    Tsuchiya, Ken'ichi; Kurosawa, Kenji; Akiba, Norimitsu; Kuroki, Kenro; Schwantes, Jon M.; Pierson, Richard; Piper, Roman K.

    2014-01-01

    Nuclear forensics are the technical means by which nuclear and other radioactive materials used in illegal activities are characterized as to physical and chemical condition, provenance, and history. Sampling for traditional forensics evidence (e.g. fingerprints, DNA, hair, fibers, and digital evidence) contaminated by radionuclides, and categorization of nuclear and other radioactive materials by on-sight measurement are required for first responders. Portable radiological equipment and radiation protection for first responders to achieve emergency tasks safely at the incident sites have been developed and evaluated in National Research Institute of Police Science. In this report, we introduce wireless network dosimetry system and neutron protection shield with water under sampling and categorization. Described next in this report are evaluation tests of active personal dosimeters using neutron irradiation field in Pacific Northwest National Laboratory. We evaluated them under fast and thermal neutron field. We confirmed the large fluctuation of the response for each dosimeter caused by the energy dependence of the detectors. (author)

  18. Derivation of parameters necessary for the evaluation of performance of sites for deep geological repositories with particular reference to bedded salt, Livermore, California. Volume I. Main text

    International Nuclear Information System (INIS)

    Ashby, J.P.; Rawlings, G.E.; Soto, C.A.; Wood, D.F.; Chorley, D.W.

    1979-12-01

    A survey of parameters to be considered in the evaluation of sites for deep geologic nuclear waste repositories is presented. As yet, no comprehensive site selection procedure or performance evaluation approach has been adopted. A basis is provided for the development of parameters by discussing both site selection and performance evaluation. Three major groups of parameters are considered in this report: geologic, mining/rock mechanics, and hydrogeologic. For each type, the role of the parameter in the evaluation of repository sites is discussed. The derivation of the parameter by measurement, correlation, inference, or other method is discussed. Geologic parameters define the framework of the repository site and can be used in development of conceptual models and the prediction of long-term performance. Methods for deriving geological parameters include mapping, surveying, drilling, geophysical investigation, and historical and regional analysis. Rock mechanics/mining parameters are essential for the prediction of short-term performance and the development of initial conditions for modeling of long-term performance. Rock mechanics/mapping parameters can be derived by field or laboratory investigation, correlation, and theoretically or empirically based inference. Hydrogeologic parameters are the most important for assessment of long-term radionuclide confinement, since transport throughout the regional hydrogeologic system is the most likely mode of radionuclide escape from geologic repositories. Hydrogeologic parameters can be derived by hydrogeologic mapping and interpretation, hydrogeologic system modeling, field measurements, and lab tests. Procedures used in determination and statistical evaluation of geologic and rock mechanics parameters are discussed

  19. Derivation of parameters necessary for the evaluation of performance of sites for deep geological repositories with particular reference to bedded salt, Livermore, California. Volume I. Main text

    Energy Technology Data Exchange (ETDEWEB)

    Ashby, J.P.; Rawlings, G.E.; Soto, C.A.; Wood, D.F.; Chorley, D.W.

    1979-12-01

    A survey of parameters to be considered in the evaluation of sites for deep geologic nuclear waste repositories is presented. As yet, no comprehensive site selection procedure or performance evaluation approach has been adopted. A basis is provided for the development of parameters by discussing both site selection and performance evaluation. Three major groups of parameters are considered in this report: geologic, mining/rock mechanics, and hydrogeologic. For each type, the role of the parameter in the evaluation of repository sites is discussed. The derivation of the parameter by measurement, correlation, inference, or other method is discussed. Geologic parameters define the framework of the repository site and can be used in development of conceptual models and the prediction of long-term performance. Methods for deriving geological parameters include mapping, surveying, drilling, geophysical investigation, and historical and regional analysis. Rock mechanics/mining parameters are essential for the prediction of short-term performance and the development of initial conditions for modeling of long-term performance. Rock mechanics/mapping parameters can be derived by field or laboratory investigation, correlation, and theoretically or empirically based inference. Hydrogeologic parameters are the most important for assessment of long-term radionuclide confinement, since transport throughout the regional hydrogeologic system is the most likely mode of radionuclide escape from geologic repositories. Hydrogeologic parameters can be derived by hydrogeologic mapping and interpretation, hydrogeologic system modeling, field measurements, and lab tests. Procedures used in determination and statistical evaluation of geologic and rock mechanics parameters are discussed.

  20. Reliability evaluation of nuclear power plants

    International Nuclear Information System (INIS)

    Rondiris, I.L.

    1978-10-01

    The research described in this thesis is concerned with the reliability/safety analysis of complex systems, such as nuclear power stations, basically using the event tree methodology. The thesis introduces and assesses a computational technique which applies the methodology to complex systems by simulating their topology and operational logic. The technique develops the system event tree and relates each branch of this tree to its qualitative and quantitative impact on specified system outcomes following an abnormal operating condition. Then, the thesis aims at deducing the critical failure modes of complex systems. This is achieved by a new technique for deducing the minimal cut or tie sets of various system outcomes. The technique is, furthermore, expanded to identify potential common mode failures and cut or tie sets containing dependent failures of some components. After dealing with the qualitative part of a reliability study, the thesis introduces two methods for calculating the probability of a component being either in the failure or in the partial failure state. The first method deals with revealed faults and makes use of the concept of Markov processes. The second one deals with unrevealed faults and can be used to calculate the relevant probability of component taking into account its inspection and replacement process. (author)

  1. Evaluation of physico-chemical and microbial parameters on water ...

    African Journals Online (AJOL)

    Microsoft Windows

    Due to heavy discharge of harmful and deleterious substances in river, the biological, chemical and ... This evaluation will be immensely helpful to estimate the effect of ... The discharge of waste water from municipal sewers containing human.

  2. Evaluation of the main parameters affecting seismic performance of ...

    Indian Academy of Sciences (India)

    The current study considers forty eight (48) 3-D RC building models to .... Acceptance criteria for members and performance level criteria for buildings are ..... Evaluation and Retrofit of Concrete Buildings, Applied Technology Council, Vol 1.

  3. Identification and evaluation of accident sequences in nuclear power reactors

    International Nuclear Information System (INIS)

    Amendola, A.; Capobianchi, S.; Mancini, G.; Olivi, L.; Volta, G.; Reina, G.

    1981-01-01

    Probabilistic analysis techniques are being more and more used for the evaluation of accident progression in nuclear power plants, especially after the issue of the Reactor Safety Study (Report WASH-1400). This study and subsequent discussions have indicated the necessity of better investigating some major items, namely: adequate data base for the probabilistic evaluations; completeness of the analysis with respect both to accident initiation and behaviour; adequate treatment of uncertainties on the physical and operational parameters governing the accident behaviour. Furthermore, recent occurrences have stressed the importance of the operational aspects of reactor safety, such as plant-specific identification of possible occurrences, their prompt recognition, on-line prediction of subsequent developments and actions to be taken. The paper reviews the contributions in progress at JRC-Ispra to all these aspects, and specifically reports on the following: (1) The set-up of a European Reliability Data System for the acquisition and organisation of operational data of LWRs in the European Community. (2) The development of more complete and realistic models of systems. This work includes multistate static models of components and systems with a view to automatic fault-tree construction and dynamic models for accident sequence identification. The dynamic modelling approach ESCS (Event Sequence and Consequences Spectrum), shown in detail with an example, represents a step forward with respect to event-tree technique and opens new possibilities in dealing with human factors and on-line diagnosis problems. (3) The development of RSM (Response Surface Methodology) for the analysis of uncertainty propagations in consequence and in probability of accident chains. (author)

  4. Conception of programs for evaluating balance indices of operation of WWER-440 nuclear power plants

    International Nuclear Information System (INIS)

    Zadrazil, J.

    1986-01-01

    The procedures are discussed of writing computation programs for the evaluation of basic technical and economic parameters of the operation of WWER-440 nuclear power plants. The criterion of the evaluation is the maximum power supply to the grid together with the required supply of heat, with the observance of safe operating conditions. Previous procedures of evaluation are compared with present procedures based on the use of a monitoring and evaluation system of the KOMPLEX-URAN 2 M type. The mathematical model of the program is based on balance equations and relations derived for actual measuring systems and is completed with an assessment of the reliability of input and output data. The flow chart is shown of the algorithm for the evaluation of technical and economic parameters, and methods are suggested for improving and extending the program. (J.C.)

  5. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Do; Lee, Jong Tae; Min, Byung Joo; Gil, Choong Sup [Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)

    1991-01-01

    In nuclear or shielding design analysis for reactors or other facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multi- group constant library using the newly compiled data files and the code systems. As the results of this project, ENDF/B-VI Supplementary File including important nuclides, JENDL-3.1 and JEF-1 were compiled, and ENDF-6 international computer file format for evaluated nuclear data and its processing system NJOY89.31 were tested with ENDF/B-VI data. In order to test an applicability of the newly released data to thermal reactor problems, a number of benchmark calculations were performed, and the results were analyzed. Since preliminary benchmark testing of thermal reactor problems have been made the newly compiled data are expected to be positively used to develop advanced reactors. (Author).

  6. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Do; Gil, Choong Sup; Min, Byung Joo; Lee, Jong Tai [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1993-01-01

    In nuclear or shielding design analysis for reactors or other facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multi-group constant library using the newly compiled data files and the code systems. As the results of this project, the latest version of NJOY nuclear data processing system, NJOY91.38 which is capable of processing data in ENDF-6 format, was compiled and installed in Cyber 960-31(OS : NOS/VE) and HP710 workstation. A 50-group constant library for fast reactor was generated with NJOY91.38 using evaluated data from JEF-1 and benchmark test of this library was performed. The newly generated library has been found to do an excellent job of calculating integral quantities for fast critical assemblies and is expected to be positively used to develop fast reactors. (Author).

  7. Nuclear data evaluation and group constant generation for reactor analysis

    International Nuclear Information System (INIS)

    Kim, Jung Do; Lee, Jong Tae; Min, Byung Joo; Gil, Choong Sup

    1991-01-01

    In nuclear or shielding design analysis for reactors or other facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multi- group constant library using the newly compiled data files and the code systems. As the results of this project, ENDF/B-VI Supplementary File including important nuclides, JENDL-3.1 and JEF-1 were compiled, and ENDF-6 international computer file format for evaluated nuclear data and its processing system NJOY89.31 were tested with ENDF/B-VI data. In order to test an applicability of the newly released data to thermal reactor problems, a number of benchmark calculations were performed, and the results were analyzed. Since preliminary benchmark testing of thermal reactor problems have been made the newly compiled data are expected to be positively used to develop advanced reactors. (Author)

  8. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D., E-mail: mencarini@ieav.cta.b, E-mail: alexdc@ieav.cta.b [Instituto de Estudos Avancados (IEAv/CTA), Sao Jose dos Campos, SP (Brazil)

    2011-07-01

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  9. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    International Nuclear Information System (INIS)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D.

    2011-01-01

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  10. Monte Carlo simulation on nuclear energy study. Annual report of Nuclear Code Evaluation Committee

    International Nuclear Information System (INIS)

    Sakurai, Kiyoshi; Yamamoto, Toshihiro

    1999-03-01

    In this report, research results discussed in 1998 fiscal year at Nuclear Code Evaluation Special Committee of Nuclear Code Committee were summarised. Present status of Monte Carlo calculation in high energy region investigated / discussed at Monte Carlo simulation working-group and automatic compilation system for MCNP cross sections developed at MCNP high temperature library compilation working-group were described. The 6 papers are indexed individually. (J.P.N.)

  11. Impact of operator on determining functional parameters of nuclear medicine procedures.

    Science.gov (United States)

    Mohammed, A M; Naddaf, S Y; Mahdi, F S; Al-Mutawa, Q I; Al-Dossary, H A; Elgazzar, A H

    2006-01-01

    The study was designed to assess the significance of the interoperator variability in the estimation of functional parameters for four nuclear medicine procedures. Three nuclear medicine technologists with varying years of experience processed the following randomly selected 20 cases with diverse functions of each study type: renography, renal cortical scans, myocardial perfusion gated single-photon emission computed tomography (MP-GSPECT) and gated blood pool ventriculography (GBPV). The technologists used the same standard processing routines and were blinded to the results of each other. The means of the values and the means of differences calculated case by case were statistically analyzed by one-way ANOVA. The values were further analyzed using Pearson correlation. The range of the mean values and standard deviation of relative renal function obtained by the three technologists were 50.65 +/- 3.9 to 50.92 +/- 4.4% for renography, 51.43 +/- 8.4 to 51.55 +/- 8.8% for renal cortical scans, 57.40 +/- 14.3 to 58.30 +/- 14.9% for left ventricular ejection fraction from MP-GSPECT and 54.80 +/- 12.8 to 55.10 +/- 13.1% for GBPV. The difference was not statistically significant, p > 0.9. The values showed a high correlation of more than 0.95. Calculated case by case, the mean of differences +/- SD was found to range from 0.42 +/- 0.36% in renal cortical scans to 1.35 +/- 0.87% in MP-GSPECT with a maximum difference of 4.00%. The difference was not statistically significant, p > 0.19. The estimated functional parameters were reproducible and operator independent as long as the standard processing instructions were followed. Copyright 2006 S. Karger AG, Basel.

  12. Qualitative Parameters for Evaluation Procedures of Non-Formal and Informal Learning Achievements

    Science.gov (United States)

    Stasiunaitiene, Egle; Kaminskiene, Lina

    2009-01-01

    The article introduces evaluation principles of non-formal and informal learning that determine the quality of evaluation, describes stages of the evaluation procedure, differentiates their qualitative parameters and defines their criteria and indicators. It also brings in the discussion that consideration of qualitative parameters for the…

  13. Some parameters of uranium hexafluoride plasma produced by products of nuclear reaction

    International Nuclear Information System (INIS)

    Batyrbekov, G.A.; Belyakova, Eh.A.

    1996-01-01

    The probe experimental results of investigation of uranium hexafluoride plasma produced in the centre of nuclear reactor core were demonstrated. Study of uranium hexafluoride plasma is continued by the following reasons: a possibility of U F 6 utilization as nuclear fuel, the utilization of U F 6 as volume source o ionization, search of active laser media compatible with U F 6 that is complicated by lack of constant rates data for most of plasma-chemical reactions with U F 6 and his dissociation products. Cylindrical probe volt-ampere characteristics (VAC) measured in U F 6 plasma at pressure 20 Torr and different thermal neutron fluxes and have following features: -firstly, it is possible to choose a linear part in the field of small positive potentials of probe (0-1) V; - secondary, ion branches of VAC have typical break which current of satiation corresponds to; -thirdly, probe VAC measured at small values of thermal neutron flux density are symmetrical. Diagnostics approaches were used for interpretation VAC of probe. The values of satiation current and linear part of electron branch were calculated, and such plasma parameters as conductivity, diffusion coefficient values of positive and negative ions were determined. The resonance recharge cross section was estimated on diffusion coefficient value

  14. Neutronic calculation of safety parameters for the RP-0 and RP-10 nuclear reactors

    OpenAIRE

    Lázaro, Gerardo; Deen, James R.; Woodruff, William L.

    2002-01-01

    Theoretical safety calculations were done with proved codes utilized by the staff of the RERTR program in the HEU to LEU core conversions. The studies were designed to evaluate the reactivity coefficients and kinetics parameters of the reactor involved in the evolution of peak power transients by reactivity insertion accidents. It was done to show the trend of these reactivity coefficients as a function of the core size and fuel depletion for RP10 cores. It was useful to get a better underst...

  15. Microscopic evaluation of the nuclear dipole polarizability

    Energy Technology Data Exchange (ETDEWEB)

    Lipparini, E; Orlandini, G; Stringari, S; Traini, M [Trento Univ. (Italy). Dept. di Matematica e Fisica

    1977-12-01

    The dipole polarizability sum rule has been evaluated by means of a restricted Hartree-Fock approach. The method leads to a simple and analytical expression for the dipole polarizability. Explicit calculations have been performed in /sup 16/O and /sup 40/Ca with different types of interaction.

  16. Evaluation Guide for the Evaluated Spent Nuclear Fuel Assay Database (SFCOMPO)

    International Nuclear Information System (INIS)

    Ortego, P.; Boulanger, D.; Gauld, I.; Gysemans, M.; Hennebach, M.; Mennerdahl, D.; Neuber, J.C.; Tore, C.; Tittelbach, S.; Van Winckel, S.; Zwicky, H.-U.

    2016-01-01

    The Expert Group on Assay Data for Spent Nuclear Fuel (EGADSNF) of the Working Party on Nuclear Criticality Safety (WPNCS) under the auspices of the NEA Nuclear Science Committee was set up in 2007 with the objective of compiling and evaluating experimental data on the nuclide compositions of irradiated nuclear fuel. Experimental data refer not only to the measured nuclide inventories and uncertainties as determined mainly by destructive radiochemical assay of spent fuel samples, but also the fuel assembly design data, reactor design information, and operating data necessary to develop benchmark models. These data provide an important basis for validating calculation methods (computer codes and nuclear data) used in fuel burn-up analyses applied to spent fuel criticality safety analyses using burnup credit, thermal analysis, radiation shielding, accident dose consequence analysis, fuel cycle safety, reprocessing, and deep geological repository safety studies. The quality and usefulness of the experimental data for methods validation can be improved by developing complete descriptions of the experiments, providing benchmark specifications, and by performing independent evaluations of the experimental and benchmark data. Evaluations of the experimental data have been identified as an important task to verify the quality of the information in the spent fuel composition (SFCOMPO) database maintained by the Nuclear Energy Agency (NEA) Data Bank. This guide defines the evaluation document format and data review procedures for evaluators tasked with reviewing the experimental data. Guidance is developed to provide recommended procedures and criteria developed by experts in the field on how to perform standardised reviews, how to identify potential problems in the measurement data and gaps in the experimental description, and provide guidance on how to resolve these issues, when possible, using a consistent technical basis. Procedures for deriving benchmark data and models

  17. Comprehensive evaluation method in application of nuclear DCS product design

    International Nuclear Information System (INIS)

    Wang Weixin; Zhao Zhemin; Shi Yingbin

    2014-01-01

    In order to select the best design proposal in short time, the TOPSIS comprehensive evaluation method in the nuclear power plant DCS product design was introduced. It can intuitively show the different design proposals good or not good by data and shorten the time of the design proposal optimization. The design proposal selected by this method will be more reasonable and has good comprehensive performance indexes. The TOPSIS comprehensive evaluation method achieves good result in one of the nuclear power plant DCS cabinet design proposal optimization. (authors)

  18. Evaluation of human error estimation for nuclear power plants

    International Nuclear Information System (INIS)

    Haney, L.N.; Blackman, H.S.

    1987-01-01

    The dominant risk for severe accident occurrence in nuclear power plants (NPPs) is human error. The US Nuclear Regulatory Commission (NRC) sponsored an evaluation of Human Reliability Analysis (HRA) techniques for estimation of human error in NPPs. Twenty HRA techniques identified by a literature search were evaluated with criteria sets designed for that purpose and categorized. Data were collected at a commercial NPP with operators responding in walkthroughs of four severe accident scenarios and full scope simulator runs. Results suggest a need for refinement and validation of the techniques. 19 refs

  19. Quantitative evaluation of physical protection system in nuclear power plant

    International Nuclear Information System (INIS)

    Sun Yahua; Li Bin; Li Shiju

    2009-01-01

    Based on the prompt detection analysis, this paper introduced one analysis model of intrusion path in nuclear power plant by means of morphology analysis and developed the evaluation software for path model analysis of physical protection system. Quantitative analysis on three elements (detection, delay, and response) of physical protection system was presented with an imaginary intrusion event example in Mac Arthur nuclear center. The results indicated that the path prompt detection analysis worked effectively to find the weak point of the physical protection system in NPP, and meantime we can also get the high cost-effectiveness improved measures. It is an effective approach to evaluate the overall performance of the system. (authors)

  20. Status of the evaluated nuclear structure data file

    International Nuclear Information System (INIS)

    Martin, M.J.

    1991-01-01

    The structure, organization, and contents of the Evaluated Nuclear Structure Data File (ENSDF) are discussed in this paper. This file contains a summary of the state of experimental nuclear structure data for all nuclides as determined from consideration of measurements reported worldwide in the literature. Special emphasis is given to the data evaluation procedures, the consistency checks, and the quality control utilized at the input stage and to the retrieval capabilities of the system at the output stage. Recent enhancements of the on-line interaction with the file contents is addressed as well as procedural changes that will improve the currency of the file

  1. Chemistry evaluation in French EDF Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jacquier, Hervé

    2014-01-01

    The Nuclear Production Division of EDF is comprised of 19 power stations (58 PWR reactors) and 2 national engineering organisations. Nuclear Inspection (IN) is an internal assessment unit of the EDF Nuclear Production Directorate. At the request of the Directorate, it carries out periodic evaluations of all the units of the division. The evaluation of the nuclear sites (EGE: Overall Excellence Assessment) is carried out every 4 years, an intermediate evaluation is also carried out between each EGE. These evaluations are independent of the WANO and IAEA evaluations. Exchanges are carried out between Nuclear Inspection and the other international operators (for example, USA (INPO), England, China...) to share site evaluation methods. These evaluations are carried out by a team of 30 inspectors, reinforced during each evaluation by 10 peers who come from the various French nuclear sites. Nuclear Inspection produces a performance standards document for each FUNCTIONAL AREA, which is based on the requirements of the company. On the whole, 13 areas are evaluated during each inspection, in particular: Management, Operations, Maintenance, Engineering and Chemistry. The area of reactor plant chemistry has been evaluated since 2009. The Chemistry performance standards document is written from the EDF internal requirements and international references. During site evaluations, all the performance standards are assessed for compliance. The Chemistry performance standards document is comprised of 3 topics: Management of plant chemistry, The respect of the chemical and radiochemical specifications, The condition of the laboratories and the sampling lines, measuring equipment, and chemical products. The evaluations carried out make it possible to define strengths and weaknesses which the sites must address. After each evaluation, the assessment is presented to the site management and to the director of EDF Nuclear Production. For 4 years these evaluations have allowed progress to

  2. Evaluation of nuclear data and their uncertainties

    International Nuclear Information System (INIS)

    Story, J.S.

    1984-01-01

    Some topics studied within the Winfrith Nuclear Data Group in recent years, and still of current importance, are briefly reviewed. Moderator cross-sections; criteria to be met for reactor applications are listed; thermal neutron scattering theory is summarized, with the approximations used to facilitate comutation; neutron age data test stringently the accuracy of epithermal cross-sections; a modification of the CFS effective range treatment for S-wave scatter by H is presented, and new calculations with up-to-date slow neutron scattering data are advocated. Use of multilevel resonance formalisms; the top bound resonance should be included explicitly in calculations; additive statistical terms are given to allow for ''distant'' negative and positive resonances, in both MLBW and R-M formalisms; formulae are presented for estimating R-M level shifts for 1>0 resonances. Resonance mean spacings; the Syson-Mehta optimum estimator is utilised in a method which up-dates the staircase plot. Resonances of 56 Fe have been resolved to approx. 800keV, over which range the level density for given Jπ should increase 2-fold; this variation is allowed for in the mean spacing calculations. Fission-product decay power; present status of integral data and summation calculations for 235 U and 239 Pu fissions is summarized, with a variety of intercomparisons including 239 Pu/ 235 U ratios. Data uncertainties are considered, but the sequence of data on GAMMAsub(γ) for the 27.8keV resonance of 56 Fe provided a cautionary example. (author)

  3. High energy nuclear data evaluations for neutron-, proton-, and photon-induced reactions at KAERI

    International Nuclear Information System (INIS)

    Lee, Young Ouk; Chang, Jong Hwa; Kim, Doo Hwan; Lee, Jeong Yeon; Han, Yinlu; Sukhovitski, Efrem Sh.

    2001-01-01

    The Korea Atomic Energy Research Institute (KAERI) is building high energy neutron-, proton-, and photon-induced nuclear data libraries for energies up to hundreds MeV in response to nuclear data needs from various R and Ds and applications. The librares provide nuclear data needed for the accelerator-driven transmutation of nuclear waste and radiation transport simulations of cancer radiotherapy. The neutron library currently has 10 isotopes such as C-12, N-14, O-16, Al-27, Si-28, Ca-40, Fe-56, Ni-58, Zr-90, Sn-120, and Pb-208 for energies from 20 up to 400 MeV. The proton nuclear data were evaluated in a consistent manner with the neutron case, using the same nuclear model parameters. In addition to the same isotopes included in the neutron library, the proton library has 70 extra isotopes of 24 elements ranging from nitrogen to lead up to 150 MeV for which the evaluations are focused on the medical and activation analyses applications. The photonuclear data library has been built along with international collaboration by participating in the IAEA's Coordinated Research Project (CRP) which ended last year. Currently the KAERI photonuclear library includes 143 isotopes of 39 elements

  4. Summary report of the 3. research co-ordination meeting on development of reference input parameter library for nuclear model calculations of nuclear data (Phase 1: Starter File)

    International Nuclear Information System (INIS)

    Oblozinsky, P.

    1997-09-01

    The report contains the summary of the third and the last Research Co-ordination Meeting on ''Development of Reference Input Parameter Library for Nuclear Model Calculations of Nuclear Data (Phase I: Starter File)'', held at the ICTP, Trieste, Italy, from 26 to 29 May 1997. Details are given on the status of the Handbook and the Starter File - two major results of the project. (author)

  5. Spanish nuclear industry experience in the evaluation of suppliers

    International Nuclear Information System (INIS)

    Ramos Pellejero, J. L.; Martinez, J. A.; Gomez, R.; Pablos, C. de; Herrero, J.

    2012-01-01

    The paper aims to present the experiences identified by the Evaluation Panel Suppliers in fulfilling its role of supplier evaluation of goods and services s afety related . It belongs to UNESA and its main objective the evaluation of the quality system of the supplier against the basic rules applicable. With it you get two main benefits: - standardize evaluation criteria share experiences between suppliers and better management of own resources. - market access to all Spanish nuclear fleet by a single evaluation. From the experience gained, it can be concluded that there is a population of highly technically qualified suppliers to meet equipment requirements.

  6. Nuclear data evaluation for medium and heavy nuclei

    International Nuclear Information System (INIS)

    Mizumoto, Motoharu

    1988-01-01

    Present status of nuclear data evaluation works for medium and heavy nuclei is described in this paper. These data are being prepared for JENDL-3 (Japanese Evaluated Nuclear Data Library-Version 3). At present, about a half of the data files, which are expected to be stored in the final library, has been brought into a temporary library called JENDL-3T. The remaining works and additional revisions are still needed to be made in order to finalize the data library as JENDL-3. Special emphases have been put on the high energy neutron data for which the previous JENDL-2 had some inadequacies, and gamma-ray production cross sections have been newly evaluated. Systematic and consistent evaluations have been intended for the new evaluations. (author)

  7. Evaluation of severe accident risks: Quantification of major input parameters

    International Nuclear Information System (INIS)

    Harper, F.T.; Payne, A.C.; Breeding, R.J.; Gorham, E.D.; Brown, T.D.; Rightley, G.S.; Gregory, J.J.; Murfin, W.; Amos, C.N.

    1991-04-01

    This report records part of the vast amount of information received during the expert judgment elicitation process that took place in support of the NUREG-1150 effort sponsored by the U.S. Nuclear Regulatory Commission. The results of the Containment Loads and Molten Core/Containment Interaction Expert Panel Elicitation are presented in this part of Volume 2 of NUREG/CR-4551. The Containment Loads Expert Panel considered seven issues: (1) hydrogen phenomena at Grand Gulf; (2) hydrogen burn at vessel breach at Sequoyah; (3) BWR reactor building failure due to hydrogen; (4) Grand Gulf containment loads at vessel breach; (5) pressure increment in the Sequoyah containment at vessel breach; (6) loads at vessel breach: Surry; and (7) pressure increment in the Zion containment at vessel breach. The report begins with a brief discussion of the methods used to elicit the information from the experts. The information for each issue is then presented in five sections: (1) a brief definition of the issue, (2) a brief summary of the technical rationale supporting the distributions developed by each of the experts, (3) a brief description of the operations that the project staff performed on the raw elicitation results in order to aggregate the distributions, (4) the aggregated distributions, and (5) the individual expert elicitation summaries. The Molten Core/Containment Interaction Panel considered three issues. The results of the following two of these issues are presented in this document: (1) Peach Bottom drywell shell meltthrough; and (2) Grand Gulf pedestal erosion. 89 figs., 154 tabs

  8. Nuclear statistics of dysprosium resonance parameters in the energy range 10 - 1000 eV

    International Nuclear Information System (INIS)

    Shin, S. G.; Kye, Y. U.; Cho, M. H.; Kim, G. N.; Namkung, W.; Lee, M. W.; Kang, Y. R.; Roe, T. I.

    2016-01-01

    A resonance parameter analysis is often performed in the Resolved Resonance Region (RRR) in order to estimate the average level spacing, distribution of the reduced widths and so on. Neutron Capture experiments on dysprosium isotopes were performed at the electron linear accelerator (LINAC) facility of the Rensselear Polytechnic Institute (RPI) in the neutron energy region from 10 eV to 1 keV. The following nuclear statistics of the resonance parameters will be discussed in this paper. The D 0 for 161 Dy and 163 Dy were judged to be constant up to 120.6 and 163.9 eV, respectively. It was assumed that the D 0 of 162 Dy and 164 Dy is constant up to 1000 eV because they have few resonances. The results were compared with the values from Reference 11 as shown in Figure 1. Statistical distributions of reduced neutron were investigated for the three isotopes in the region from 0 to 1000 eV; 161 Dy, 162 Dy, and 163 Dy, but not for 164 Dy because of a few number of resonances. The reduced neutron widths Γ n 0 were divided by the unweighted average reduced neutron width < Γ n 0 > for each isotope. A cumulative distribution of these unitless ratios is compared with the integral of the Porter-Thomas distribution (χ 2 distribution with one degree of freedom). The results agree reasonably with the Porter Thomas distributions.

  9. Integration of neural networks with fuzzy reasoning for measuring operational parameters in a nuclear reactor

    International Nuclear Information System (INIS)

    Ikonomopoulos, A.; Tsoukalas, L.H.

    1993-01-01

    A novel approach is described for measuring variables with operational significance in a complex system such as a nuclear reactor. The methodology is based on the integration of artificial neural networks with fuzzy reasoning. Neural networks are used to map dynamic time series to a set of user-defined linguistic labels called fuzzy values. The process takes place in a manner analogous to that of measurement. Hence, the entire procedure is referred to as virtual measurement and its software implementation as a virtual measuring device. An optimization algorithm based on information criteria and fuzzy algebra augments the process and assists in the identification of different states of the monitored parameter. The proposed technique is applied for monitoring parameters such as performance, valve position, transient type, and reactivity. The results obtained from the application of the neural network-fuzzy reasoning integration in a high power research reactor clearly demonstrate the excellent tolerance of the virtual measuring device to faulty signals as well as its ability to accommodate noisy inputs

  10. Assessment on Evaluating Parameters of Rice Core Collections Constructed by Genotypic Values and Molecular Marker Information

    Directory of Open Access Journals (Sweden)

    Jian-cheng WANG

    2007-06-01

    Full Text Available Eleven evaluating parameters for rice core collection were assessed based on genotypic values and molecular marker information. Monte Carlo simulation combined with mixed linear model was used to eliminate the interference from environment in order to draw more reliable results. The coincidence rate of range (CR was the optimal parameter. Mean Simpson index (MD, mean Shannon-Weaver index of genetic diversity (MI and mean polymorphism information content (MPIC were important evaluating parameters. The variable rate of coefficient of variation (VR could act as an important reference parameter for evaluating the variation degree of core collection. Percentage of polymorphic loci (p could be used as a determination parameter for the size of core collection. Mean difference percentage (MD was a determination parameter for the reliability judgment of core collection. The effective evaluating parameters for core collection selected in the research could be used as criteria for sampling percentage in different plant germplasm populations.

  11. Computer code ENDSAM for random sampling and validation of the resonance parameters covariance matrices of some major nuclear data libraries

    International Nuclear Information System (INIS)

    Plevnik, Lucijan; Žerovnik, Gašper

    2016-01-01

    Highlights: • Methods for random sampling of correlated parameters. • Link to open-source code for sampling of resonance parameters in ENDF-6 format. • Validation of the code on realistic and artificial data. • Validation of covariances in three major contemporary nuclear data libraries. - Abstract: Methods for random sampling of correlated parameters are presented. The methods are implemented for sampling of resonance parameters in ENDF-6 format and a link to the open-source code ENDSAM is given. The code has been validated on realistic data. Additionally, consistency of covariances of resonance parameters of three major contemporary nuclear data libraries (JEFF-3.2, ENDF/B-VII.1 and JENDL-4.0u2) has been checked.

  12. I. Nuclear and neutron matter calculations with isobars. II. A model calculation of Fermi liquid parameters for liquid 3He

    International Nuclear Information System (INIS)

    Ainsworth, T.L.

    1983-01-01

    The Δ(1232) plays an important role in determining the properties of nuclear and neutron matter. The effects of the Δ resonance are incorporated explicitly by using a coupled channel formalism. A method for constraining a lowest order variational calculation, appropriate when nucleon internal degrees of freedom are made explicity, is presented. Different N-N potentials were calculated and fit to phase shift data and deuteron properties. The potentials were constructed to test the relative importance of the Δ resonance on nuclear properties. The symmetry energy and incompressibility of nuclear matter are generally reproduced by this calculation. Neutron matter results lead to appealing neutron star models. Fermi liquid parameters for 3 He are calculated with a model that includes both direct and induced terms. A convenient form of the direct interaction is obtained in terms of the parameters. The form of the direct interaction ensures that the forward scattering sum rule (Pauli principle) is obeyed. The parameters are adjusted to fit the experimentally determined F 0 /sup s/, F 0 /sup a/, and F 1 /sup s/ Landau parameters. Higher order Landau parameters are calculated by the self-consistent solution of the equations; comparison to experiment is good. The model also leads to a preferred value for the effective mass of 3 He. Of the three parameters only one shows any dependence on pressure. An exact sum rule is derived relating this parameter to a specific summation of Landau parameters

  13. EVALUATION OF FERMENTATION PARAMETERS DURING HIGH-GRAVITY BEER PRODUCTION

    Directory of Open Access Journals (Sweden)

    R.B. Almeida

    2001-12-01

    Full Text Available A large number of advantages are obtained from the use of highly concentrated worts during the production of beer in a process referred to as "high-gravity". However, problems related to slow or stuck fermentations, which cause the lower productivity and possibility of contamination, are encountered. This study examines the influence of factors pH, percentage of corn syrup, initial wort concentration and fermentation temperature on the fermentation parameters, namely productivity, wort attenuation and the yield coefficient for sugar-to-ethanol conversion. The results show that productivity increased when the higher temperature, the higher wort concentration and the lower syrup percentage were used, while wort attenuation increased when lower wort concentration and no syrup were used. The yield coefficient for sugar-to-ethanol conversion was not influenced by any of the factors studied.

  14. Evaluating System Parameters on a Dragonfly using Simulation and Visualization

    Energy Technology Data Exchange (ETDEWEB)

    Bhatele, Abhinav [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jain, Nikhil [Univ. of Illinois, Urbana-Champaign, IL (United States); Livnat, Yarden [Univ. of Utah, Salt Lake City, UT (United States); Pascucci, Valerio [Univ. of Utah, Salt Lake City, UT (United States); Bremer, Peer-Timo [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Univ. of Utah, Salt Lake City, UT (United States)

    2015-04-24

    The dragon y topology is becoming a popular choice for build- ing high-radix, low-diameter networks with high-bandwidth links. Even with a powerful network, preliminary experi- ments on Edison at NERSC have shown that for communica- tion heavy applications, job interference and thus presumably job placement remains an important factor. In this paper, we explore the e ects of job placement, job sizes, parallel workloads and network con gurations on network through- put to better understand inter-job interference. We use a simulation tool called Damsel y to model the network be- havior of Edison and study the impact of various system parameters on network throughput. Parallel workloads based on ve representative communication patters are used and the simulation studies on up to 131,072 cores are aided by a new visualization of the dragon y network.

  15. Evaluation of Physicochemical and Microbiological Parameters of Smoked Sausages

    Directory of Open Access Journals (Sweden)

    Melinda Nagy

    2015-11-01

    Full Text Available Meat and meat products continue to supply nutrients and play a vital role in human life because of their high biological value protein, iron, zinc, selenium and vitamin B12 contents, being a crucial component of a well balanced diet. The objective of this paper was to analyse the microbiological and physicochemical characteristics of smoked sausage obtain by a modern recipe. The meat  material was obtained from local butchery (Cluj-Napoca, Romania. The physicochemical analyses highlighted the moisture (Drying-oven at 105 ºC, protein (Kjeldahl method and fat (Soxhlet method content, as well as nitrite (Griess method and sodium chloride concentrations (Mohr method of the final products. Microbiological and physicochemical analysis of the examined samples found no deviations from legal norms imposed for smoked sausage.  All of the quality parameters comply with the limits stipulated by STAS. 

  16. The evaluation of environmental effects of nuclear power plants

    International Nuclear Information System (INIS)

    Oezyurt, M.; Iyit, L.; Seyitogullari, S.

    2006-01-01

    Energy is today one of the most significant topics in the world. Humans are investigating alternative energy resources due to the fossil energy sources to be exhausted in future. As known, the life of energy resources such as coal and oil is limited. Natural gas will cover the need just for a limited period. On the other hand, developing population will increase the need of energy for the next generation. Therefore, alternative energy has gained much significance in recent years. Nuclear energy is the most criticized energy in public opinion. About 17 pct. of the electric need in the world is being covered by nuclear power plants . This ratio is over 30 pct. in European Union and over 78.2 pct. in France. The most significant risk as regard with environmental pollution is radioactive wastes for these plants. The opposite sides towards nuclear energy claim about the accidents of nuclear power plants and deaths in short and long terms. As long as the security rules are applied, nuclear power plants affect neither human nor environmental health in a detrimental way. The radiation emission scattered by nuclear power plants is very low. In this work, first of all nuclear energy was evaluated from a standpoint of environmental pollution and both positive and negative effects were investigated. As a result, the humanity will have to benefit from all the alternative energy resources , the nuclear energy as well, in order not to live in a dark world. Every technology has its own risks. It seems that if nuclear energy power plants are operated in high technology conditions it will be un given up for humanity

  17. Estimation of physiological parameters using knowledge-based factor analysis of dynamic nuclear medicine image sequences

    International Nuclear Information System (INIS)

    Yap, J.T.; Chen, C.T.; Cooper, M.

    1995-01-01

    The authors have previously developed a knowledge-based method of factor analysis to analyze dynamic nuclear medicine image sequences. In this paper, the authors analyze dynamic PET cerebral glucose metabolism and neuroreceptor binding studies. These methods have shown the ability to reduce the dimensionality of the data, enhance the image quality of the sequence, and generate meaningful functional images and their corresponding physiological time functions. The new information produced by the factor analysis has now been used to improve the estimation of various physiological parameters. A principal component analysis (PCA) is first performed to identify statistically significant temporal variations and remove the uncorrelated variations (noise) due to Poisson counting statistics. The statistically significant principal components are then used to reconstruct a noise-reduced image sequence as well as provide an initial solution for the factor analysis. Prior knowledge such as the compartmental models or the requirement of positivity and simple structure can be used to constrain the analysis. These constraints are used to rotate the factors to the most physically and physiologically realistic solution. The final result is a small number of time functions (factors) representing the underlying physiological processes and their associated weighting images representing the spatial localization of these functions. Estimation of physiological parameters can then be performed using the noise-reduced image sequence generated from the statistically significant PCs and/or the final factor images and time functions. These results are compared to the parameter estimation using standard methods and the original raw image sequences. Graphical analysis was performed at the pixel level to generate comparable parametric images of the slope and intercept (influx constant and distribution volume)

  18. Theoretical and experimental evaluation of piezo-optic parameters and photoelastic constant in tetragonal PWO.

    Science.gov (United States)

    Natali, Pier Paolo; Montalto, Luigi; Daví, Fabrizio; Mengucci, Paolo; Ciriaco, Andrea; Paone, Nicola; Rinaldi, Daniele

    2018-02-01

    The tetragonal PbWO 4 (PWO) is one of the most important scintillating crystals, being used both in the Compact Muon Solenoid (CMS) experiment at the European Organization for Nuclear Research (CERN) and in the PANDA project at the Facility for Antiproton and Ion Research (FAIR). Light yield and other relevant scintillation properties depend, among many factors, also on the crystal mechanical quality. Accordingly, a detailed knowledge of crystal piezo-optic properties is a mandatory step toward understanding elasto-optic behavior and performing crystal quality control. In this paper, we evaluate for the first time, to the best of our knowledge, by means of both photoelastic and x-ray measurements, some components of the piezo-optic tensor; moreover, when the crystal is acted upon by a uniaxial stress, we obtain an evaluation for the rotation angle of the optic plane under stress as well as the photoelastic constant. These parameters are necessary to detect the residual stresses within the crystal, if any, and to give an overall quality measure. Such a methodology is in general suitable for any tetragonal crystals.

  19. Development of expert evaluation system for advanced nuclear power stations

    International Nuclear Information System (INIS)

    Yang Mengjia; Ren Junsheng; Zhou Zhiwei; Zhang Qi; Zhu Shutang

    2005-01-01

    The wheels of the nuclear power industry in China are going to roll on the fast rails soon: It is important to establish an expert evaluation system for optimally selecting new types of NPPs in the future based on scientific evaluation. Under such a background, an expert evaluation system is developed to evaluate Various types of NPPs for the following two decades by taking into account the advices of selected top specialists in Chinese nuclear power industry, and by adopting different evaluation methods. The evaluation system is designed to use the database-MS-SQL Server or Oracle for manipulating experts' knowledge and objective data for scaling NPPs by user-selected evaluation methods for evaluating NPPs. The system includes two subsystems: one is called the Data Management Module and the other called the Evaluation Arithmetic Module. The Data Management Module is used to manage expert knowledge in forms of item marks of the NPPs given by experts of nuclear engineering. The Evaluation Arithmetic Module is used to analyze and deal with the evaluation based on the data in the Database by certain designed evaluation method, and to provide the evaluation results. Based on the users' selection, the evaluation of the NPPs is processed, and the results can be dynamically listed in table or displayed in graphics. So it can be used as a consulting tool to help users make optimal selection of prospective NPPs. The system is developed in architecture of the mixture framework C/S(Client/Server) and B/S(Browse/Server), thus is safe, advanced, extensible and user- friendly. The present system is computer network based, so it can be used not only in personal PC and local network, but also in the Web Server which can be browsed by remote users. To develop such an evaluation system is an initiative R and D project in Chinese nuclear R and D activities. Although the evaluation system is far from perfect, however, the preliminary evaluation results produced by the evaluation

  20. RIDE vs. CLASP Comparison and Evaluation: Models and Parameters

    Science.gov (United States)

    2007-04-01

    the model is declared "No Decision," indicating that neither QLRM nor LLRM provides a satisfactory fit. If p-value ( i 2j ) > p-value ( flj ), then our...evaluated at A = D = loo tD (7) UA/D(70,40) = 37.35 (8) UA/D(70,100) = 22.93 (9) OUA/D = 0 when evaluated at A = 70, D = 65.7 aD Note the number of...M U) U) C)U)f-~H W 0 U) co CQ CU)QC) W W 0 O40U) El)U tq D O U) U) E U) Z 04 X L X 4j c)c: o n n , f)cj" D ,m u)o mm o:zz .o tD o U) Uti)U) ’-4 r-4

  1. Evaluation of Stress Parameters Based on Heart Rate Variability Measurements

    OpenAIRE

    Uysal, Fatma; Tokmakçı, Mahmut

    2018-01-01

    In this study, heart rate variabilitymeasurements and analysis was carried with help of the ECG recordings to showhow autonom nervous system activity changes. So as to evaluate the parametersrelated to stress of the study, the situation of relaxation, Stroop color/wordtest, mental test and auditory stimulus that would stress someone out wereapplied to six volunteer participants in a laboratory environment. Being takentotally seven minutes ECG recording and made analysis in time and frequencyd...

  2. Development of life evaluation technology for nuclear power plant components

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin [Sungkyunkwan Univ., Seoul (Korea, Republic of); Kwon, J. D. [Yeungnam Univ., Gyeongsan (Korea, Republic of); Kang, K. J. [Chonnam National Univ., Gwangju (Korea, Republic of)] (and others)

    2001-03-15

    This research focuses on development of reliable life evaluation technology for nuclear power plant (NPP) components, and is divided into two parts, development of life evaluation systems for pressurized components and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered: development of expert systems for integrity assessment of pressurized components, development of integrity evaluation systems of steam generator tubes, prediction of failure probability for NPP components based on probabilistic fracture mechanics, development of fatigue damage evaluation technique for plant life extension, domestic round robin analysis for pressurized thermal shock of reactor vessels, domestic round robin analysis of constructing P--T limit curves for reactor vessels, and development of data base for integrity assessment. For evaluation of applicability of emerging technology to operating plants, on the other hand, the following eight topics are covered: applicability of the Leak-Before-Break analysis to Cast S/S piping, collection of aged material tensile and toughness data for aged Cast S/S piping, finite element analyses for load carrying capacity of corroded pipes, development of Risk-based ISI methodology for nuclear piping, collection of toughness data for integrity assessment of bi-metallic joints, applicability of the Master curve concept to reactor vessel integrity assessment, measurement of dynamic fracture toughness, and provision of information related to regulation and plant life extension issues.

  3. Fatigue damage evaluation of stainless steel pipes in nuclear power plants using positron annihilation lineshape analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kawaguchi, Yasuhiro [Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan); Nakamura, Noriko; Yusa, Satoru [Ishikawajima-Harima Heavy Industries Co., Tokyo (Japan)

    2002-09-01

    Since positron annihilation lineshape analysis can evaluate the degree of fatigue damage by detecting defects such as dislocations in metals, we applied this method to evaluate that in a type 316 stainless steel pipe which was used in the primary system of a nuclear power plant. Using {sup 68}Ge as a positron source, an energy spread of annihilation gamma ray peak from the material was measured and expressed as the S-parameter. Actual plant material cut from a surge line pipe of a pressurizer in a pressurized water reactor type nuclear power plant was measured by positron annihilation lineshape analysis and the S-parameter was obtained. Comparing the S-parameter with a relationship between the S-parameter and fatigue life ratio of the type 316 stainless steel, we evaluated the degree of fatigue damage of the actual material. Furthermore, to verify the evaluation, microstructures of the actual material were investigated with TEM (transmission electron microscope) to observe dislocation densities. As a result, a change in the S-parameter of the actual material from standard as-received material (type 316 stainless steel) was in the range from -0.0013 to 0.0014, while variations in the S-parameter of the standard as-received material were about {+-}0.002, and hence the differences between the actual material and the as-received material were negligible. Moreover, the dislocation density of the actual plant material observed with TEM was almost the same as that of the as-received one. In conclusion, we could confirm the applicability of the positron annihilation lineshape analysis to fatigue damage evaluation of stainless steel. (author)

  4. Risk-benefit evaluation of nuclear power plant siting

    International Nuclear Information System (INIS)

    Miettinen, J.; Savolainen, I.; Silvennoinen, P.

    1976-01-01

    An assessment scheme is described for the risk-benefit analyses of nuclear power versus conventional alternatives. Given the siting parameters for the proposed nuclear plant an economic comparison is made with the most advantageous competitive conventional production scenario. The economic benefit is determined from the differential discounted annual energy procurement cost as a function of the real interest rate and amortization time. The risk analysis encompasses the following factors: radiation risks in normal operation, reactor accident hazards and economic risks, atmospheric pollutants from the conventional power plants, and fuel transportation. The hazards are first considered in terms of probabilistic dose distributions. In the second stage risk components are converted to a compatible form where excess mortality is used as the risk indicator. Practical calculations are performed for the power production alternatives of Helsinki where district heat would be extracted from the nuclear power plant. At the real interest rate of 10% and amortization time of 20 yr the 1000 MW(e) nuclear option is found to be Pound9.1 m per yr more economic than the optimal conventional scenario. Simultaneously the nuclear alternative is estimated to reduce excess mortality by 2 to 5 fatal injuries annually. (author)

  5. Evaluation of accelerated test parameters for CMOS IC total dose hardness prediction

    International Nuclear Information System (INIS)

    Sogoyan, A.V.; Nikiforov, A.Y.; Chumakov, A.I.

    1999-01-01

    The approach to accelerated test parameters evaluation is presented in order to predict CMOS IC total dose behavior in variable dose-rate environment. The technique is based on the analytical model of MOSFET parameters total dose degradation. The simple way to estimate model parameter is proposed using IC's input-output MOSFET radiation test results. (authors)

  6. Emergy Evaluation of a Swedish Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kindberg, Anna

    2007-03-01

    Today it is common to evaluate and compare energy systems in terms of emission of greenhouse gases. However, energy systems should not only reduce their pollution but also give a large energy return. One method used to measure energy efficiency is emergy (embodied energy, energy memory) evaluation, which was developed by the system ecologist Howard T. Odum. Odum defines emergy as the available energy of one kind previously used up directly and indirectly to make a service or product. Both work of nature and work of human economy in generating products and services are calculated in terms of emergy. Work of nature takes the form of natural resources and work of human economy includes labour, services and products used to transform natural resources into something of value to the economy. The quotient between work of nature and work of human economy gives the emergy return on investment of the investigated product. With this in mind the present work is an attempt to make an emergy evaluation of a Swedish nuclear power plant to estimate its emergy return on investment. The emergy return on investment ratio of a Swedish nuclear power plant is calculated to approximately 11 in this diploma thesis. This means that for all emergy the Swedish economy has invested in the nuclear power plant it gets 11 times more emergy in return in the form of electricity generated by nuclear power. The method used in this work may facilitate future emergy evaluations of other energy systems

  7. Opinions on nuclear energy: Evaluations, beliefs, and attitudes.

    NARCIS (Netherlands)

    Meertens, R.W.; Stallen, P.J.

    1981-01-01

    Used the expectancy-value model of attitudes (M. Fishbein and I. Ajzen, 1975) to investigate the attitudes, evaluations, and beliefs concerning the peaceful use of nuclear energy in 252 Dutch social and natural scientists. The model received empirical support. A factor analysis revealed 2

  8. Evaluation of radiation protection conditions in nuclear gauges fabrication

    International Nuclear Information System (INIS)

    Sekiguchi, Marcelo Ferreira; Borges, Jose Carlos

    1999-01-01

    The objective of this work was to evaluate the radioprotection conditions in the work place, of a industry that produces nuclear gauges. The survey was divided, basically, in two parts; first took place a physical monitoring area, individual and contamination and biological, through the analysis of excretes and cytogenetic dosimetry. (author)

  9. Evaluation and assessment of nuclear power plant seismic methodology

    Energy Technology Data Exchange (ETDEWEB)

    Bernreuter, D.; Tokarz, F.; Wight, L.; Smith, P.; Wells, J.; Barlow, R.

    1977-03-01

    The major emphasis of this study is to develop a methodology that can be used to assess the current methods used for assuring the seismic safety of nuclear power plants. The proposed methodology makes use of system-analysis techniques and Monte Carlo schemes. Also, in this study, we evaluate previous assessments of the current seismic-design methodology.

  10. Evaluation and assessment of nuclear power plant seismic methodology

    International Nuclear Information System (INIS)

    Bernreuter, D.; Tokarz, F.; Wight, L.; Smith, P.; Wells, J.; Barlow, R.

    1977-01-01

    The major emphasis of this study is to develop a methodology that can be used to assess the current methods used for assuring the seismic safety of nuclear power plants. The proposed methodology makes use of system-analysis techniques and Monte Carlo schemes. Also, in this study, we evaluate previous assessments of the current seismic-design methodology

  11. Fracture mechanics and fatigue evaluation of nuclear reactor components

    International Nuclear Information System (INIS)

    Mattar Neto, Miguel; Andrade, Arnaldo H.P. de; Maneschy, Eduardo

    1995-01-01

    This paper presents a theoretical study available in the available literature for evaluation the environmental effects on the lifetime of nuclear power plant components. The author's motivation is to provide some technical tools to identify what research development could be done in this area

  12. Evaluation of seismic hazards for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    The main objective of this Safety Guide is to provide recommendations on how to determine the ground motion hazards for a plant at a particular site and the potential for surface faulting, which could affect the feasibility of construction and safe operation of a plant at that site. The guidelines and procedures presented in this Safety Guide can appropriately be used in evaluations of site suitability and seismic hazards for nuclear power plants in any seismotectonic environment. The probabilistic seismic hazard analysis recommended in this Safety Guide also addresses the needs for seismic hazard analysis of external event PSAs conducted for nuclear power plants. Many of the methods and processes described may also be applicable to nuclear facilities other than power plants. Other phenomena of permanent ground displacement (liquefaction, slope instability, subsidence and collapse) as well as the topic of seismically induced flooding are treated in Safety Guides relating to foundation safety and coastal flooding. Recommendations of a general nature are given in Section 2. Section 3 discusses the acquisition of a database containing the information needed to evaluate and address all hazards associated with earthquakes. Section 4 covers the use of this database for construction of a seismotectonic model. Sections 5 and 6 review ground motion hazards and evaluations of the potential for surface faulting, respectively. Section 7 addresses quality assurance in the evaluation of seismic hazards for nuclear power plants

  13. Emergy Evaluation of a Swedish Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kindberg, Anna

    2007-03-15

    Today it is common to evaluate and compare energy systems in terms of emission of greenhouse gases. However, energy systems should not only reduce their pollution but also give a large energy return. One method used to measure energy efficiency is emergy (embodied energy, energy memory) evaluation, which was developed by the system ecologist Howard T. Odum. Odum defines emergy as the available energy of one kind previously used up directly and indirectly to make a service or product. Both work of nature and work of human economy in generating products and services are calculated in terms of emergy. Work of nature takes the form of natural resources and work of human economy includes labour, services and products used to transform natural resources into something of value to the economy. The quotient between work of nature and work of human economy gives the emergy return on investment of the investigated product. With this in mind the present work is an attempt to make an emergy evaluation of a Swedish nuclear power plant to estimate its emergy return on investment. The emergy return on investment ratio of a Swedish nuclear power plant is calculated to approximately 11 in this diploma thesis. This means that for all emergy the Swedish economy has invested in the nuclear power plant it gets 11 times more emergy in return in the form of electricity generated by nuclear power. The method used in this work may facilitate future emergy evaluations of other energy systems.

  14. Evaluation of vibratory ground motion at nuclear power plant sites

    International Nuclear Information System (INIS)

    Hofmann, R.B.; Greeves, J.T.

    1978-01-01

    The evaluation of vibratory ground motion at nuclear power plant sites requires the cooperative effort of scientists and engineers in several disciplines. These include seismology, geology, geotechnical engineering and structural engineering. The Geosciences Branch of the NRC Division of Site Safety and Environmental Analysis includes two sections, the Geology/Seismology Section and the Geotechnical Engineering Section

  15. Evaluation of ground stiffness parameters using continuous surface wave geophysics

    DEFF Research Database (Denmark)

    Gordon, Anne; Foged, Niels

    2000-01-01

    Present day knowledge of the magnitude of the strain levels in the ground associated with geotechnical structures, together with an increasing number of projects requiring the best estimates of ground movements around excavations, has led to, inter alia, increased interest in measuring the very......-small-strain stiffness of the ground Gmax. Continuous surface wave geophysics offers a quick, non-intrusive and economical way of making such measurements. This paper reviews the continuous surface wave techniques and evaluates, in engineering terms, the applicability of the method to the site investigation industry....

  16. Aging Evaluation of Nuclear Power Plant Concrete Structures

    International Nuclear Information System (INIS)

    Kitsutaka, Y.; Takesue, N.; Tsukagoshi, M.

    2012-01-01

    In this paper, method on the aging evaluation in nuclear power plant concrete structures was investigated. Problems on the durability evaluation of reinforced concrete structures were pointed out and an evaluation framework was considered. In view of the importance of evaluating the degree of deterioration of reinforced concrete structures, relationships should be formulated among the number of years elapsed, t, the amount of action of a deteriorative factor, F, the degree of material deterioration, D, and the performance of the structure, P. Evaluation by PDFt diagrams combining these relationships may be effective. A detailed procedure of durability evaluation for a reinforced concrete structure using PDFt concept is presented for the deterioration factors of thermal effect, irradiation, neutralization and penetration of salinity by referring to the recent papers. And the evaluation framework of the deteriorated material constitutive model which can be used for the numerical analysis of the integrity evaluation for the concrete structure was proposed. (author)

  17. Evaluation for nuclear safety-critical software reliability of DCS

    International Nuclear Information System (INIS)

    Liu Ying

    2015-01-01

    With the development of control and information technology at NPPs, software reliability is important because software failure is usually considered as one form of common cause failures in Digital I and C Systems (DCS). The reliability analysis of DCS, particularly qualitative and quantitative evaluation on the nuclear safety-critical software reliability belongs to a great challenge. To solve this problem, not only comprehensive evaluation model and stage evaluation models are built in this paper, but also prediction and sensibility analysis are given to the models. It can make besement for evaluating the reliability and safety of DCS. (author)

  18. Evaluation of nuclear magnetic resonance spectroscopy variability

    Energy Technology Data Exchange (ETDEWEB)

    Barreto, Felipe Rodrigues; Salmon, Carlos Ernesto Garrido, E-mail: garrido@ffclrp.usp.br [Universidade de Sao Paulo (FFCLRP/USP), Ribeirao Preto, SP (Brazil). Fac. de Filisofia, Ciencias e Letras; Otaduy, Maria Concepcion Garcia [Universidade de Sao Paulo (FAMUS/USP), Sao Paulo, SP (Brazil). Fac. de Medicina. Departamento de Radiologia

    2014-11-01

    Introduction: the intrinsically high sensitivity of Magnetic Resonance Spectroscopy (MRS) causes considerable variability in metabolite quantification. In this study, we evaluated the variability of MRS in two research centers using the same model of magnetic resonance image scanner. Methods: two metabolic phantoms were created to simulate magnetic resonance spectra from in vivo hippocampus. The phantoms were filled with the same basic solution containing the following metabolites: N-acetyl-aspartate, creatine, choline, glutamate, glutamine and inositol. Spectra were acquired over 15 months on 26 acquisition dates, resulting in a total of 130 spectra per center. Results: the phantoms did not undergo any physical changes during the 15-month period. Temporal analysis from both centers showed mean metabolic variations of 3.7% in acquisitions on the same day and of 8.7% over the 15-month period. Conclusion: The low deviations demonstrated here, combined with the high specificity of Magnetic Resonance Spectroscopy, confirm that it is feasible to use this technique in multicenter studies in neuroscience research. (author)

  19. Comparative evaluation of qigong on various parameters of saliva

    Directory of Open Access Journals (Sweden)

    Bayat Movahed S.

    2007-05-01

    Full Text Available Background and Aim: Qigong is a type of Chinese psychosomatic exercise that integrates meditation, slow physical movements, and breathing. Numerous physical and mental benefits have been classically ascribed to qigong. On the other hand, unstimulated saliva is thought to play an important role in oral immunity, enamel stability and moisturizing the oral mucous membrane. Impaired salivary secretion leads to dental caries, mucosal deterioration and mouth dryness. The aim of the present study was to analyze the effect of a qigong program on various parameters of saliva such as quantity of unstimulated saliva, pH and SIgA. Materials and Methods: Twenty three subjects participated in this clinical trial study. The experimental subjects underwent a qigong training program, conducted by a qualified instructor. The program consisted of half an hour daily practice for 6 months (spring and winter. Saliva was collected in two periods: once during the spring before the experiment commencement and the second, in the following spring. During each period saliva collection was done on tuesday of each week. pH and quantity of salvia measurements were taken simultaneously. SIgA measurements were also taken based on the values obtained in the last phase of the experiment at the end of each spring. The results were analyzed using paired sample T test, one way repeated measure and Bon Ferroni multiple comparison. P<0.05 was the level of significance. Results: Based on our findings, the change in the amount of unstimulated salvia as well as SIgA was statistically significant (P<0.001; however, there was no significant difference in pH values before and after experiment. Conclusion: These findings demonstrate that after 6 months of practicing qigong, significant changes in amount of unstimulated saliva and SIgA occurred in participants. The authors suggest that qigong may be a beneficial adjunctive treatment that enhances amount of unstimulated saliva and SIgA.

  20. The Nuclear Renaissance — Implications on Quantitative Nondestructive Evaluations

    Science.gov (United States)

    Matzie, Regis A.

    2007-03-01

    The world demand for energy is growing rapidly, particularly in developing countries that are trying to raise the standard of living for billions of people, many of whom do not even have access to electricity. With this increased energy demand and the high and volatile price of fossil fuels, nuclear energy is experiencing resurgence. This so-called nuclear renaissance is broad based, reaching across Asia, the United States, Europe, as well as selected countries in Africa and South America. Some countries, such as Italy, that have actually turned away from nuclear energy are reconsidering the advisability of this design. This renaissance provides the opportunity to deploy more advanced reactor designs that are operating today, with improved safety, economy, and operations. In this keynote address, I will briefly present three such advanced reactor designs in whose development Westinghouse is participating. These designs include the advanced passive PWR, AP1000, which recently received design certification for the US Nuclear Regulatory Commission; the Pebble Bed Modular reactor (PBMR) which is being demonstrated in South Africa; and the International Reactor Innovative and Secure (IRIS), which was showcased in the US Department of Energy's recently announced Global Nuclear Energy Partnership (GNEP), program. The salient features of these designs that impact future requirements on quantitative nondestructive evaluations will be discussed. Such features as reactor vessel materials, operating temperature regimes, and new geometric configurations will be described, and mention will be made of the impact on quantitative nondestructive evaluation (NDE) approaches.

  1. The Nuclear Renaissance - Implications on Quantitative Nondestructive Evaluations

    International Nuclear Information System (INIS)

    Matzie, Regis A.

    2007-01-01

    The world demand for energy is growing rapidly, particularly in developing countries that are trying to raise the standard of living for billions of people, many of whom do not even have access to electricity. With this increased energy demand and the high and volatile price of fossil fuels, nuclear energy is experiencing resurgence. This so-called nuclear renaissance is broad based, reaching across Asia, the United States, Europe, as well as selected countries in Africa and South America. Some countries, such as Italy, that have actually turned away from nuclear energy are reconsidering the advisability of this design. This renaissance provides the opportunity to deploy more advanced reactor designs that are operating today, with improved safety, economy, and operations. In this keynote address, I will briefly present three such advanced reactor designs in whose development Westinghouse is participating. These designs include the advanced passive PWR, AP1000, which recently received design certification for the US Nuclear Regulatory Commission; the Pebble Bed Modular reactor (PBMR) which is being demonstrated in South Africa; and the International Reactor Innovative and Secure (IRIS), which was showcased in the US Department of Energy's recently announced Global Nuclear Energy Partnership (GNEP), program. The salient features of these designs that impact future requirements on quantitative nondestructive evaluations will be discussed. Such features as reactor vessel materials, operating temperature regimes, and new geometric configurations will be described, and mention will be made of the impact on quantitative nondestructive evaluation (NDE) approaches

  2. Evaluation of new multiaxial damage parameters on low carbon steel

    Directory of Open Access Journals (Sweden)

    A. S. Cruces

    2017-07-01

    Full Text Available Most mechanical components are subjected to the complex fatigue loading conditions, where both amplitude and direction of loading cycles change over the time. The estimation of damage caused by these complex loading scenarios are often done by simplified uniaxial fatigue theories, which ultimately leads to higher factor of safety during the final design considerations. Critical plane-based fatigue theories have been considered more accurate for computing the fatigue damage for multiaxial loading conditions in comparison to energy-based and equivalent stress-based theories. Two recently developed fatigue theories have been evaluated in this work for the available test data. Test data includes significant amount of biaxial load paths.

  3. The choice of equipment mix and parameters for HTGR-based nuclear cogeneration plants

    Energy Technology Data Exchange (ETDEWEB)

    Malevski, A L; Stoliarevski, A Ya; Vladimirov, V T; Larin, E A; Lesnykh, V V; Naumov, Yu V; Fedotov, I L

    1990-07-01

    Improvement of heat and electricity supply systems based on cogeneration is one of the high-priority problems in energy development of the USSR. Fossil fuel consumption for heat supply exceeds now its use for electricity production and amounts to about 30% of the total demands. District heating provides about 80 million t.c.e. of energy resources conserved annually and meets about 50% of heat consumption of the country, including about 30% due to cogeneration. The share of natural gas and liquid fuel in the fuel consumption for district heating is about 70%. The analysis of heat consumption dynamics in individual regions and industrial-urban agglomerations shows the necessity of constructing cogeneration plants with the total capacity of about 60 million kW till the year 2000. However, their construction causes some serious problems. The most important of them are provision of environmentally clean fuels for cogeneration plants and provision of clear air. The limited reserves of oil and natural gas and the growing expenditures on their production require more intensive introduction of nuclear energy in the national energy balance. Possible use of nuclear energy based on light-water reactors for substitution of deficient hydrocarbon fuels is limited by the physical, technical and economic factors and requirements of safety. Further development of nuclear energy in the USSR can be realized on a new technological base with construction of domestic reactors of increased and ultimate safety. The most promising reactors under design are high-temperature gas-cooled reactors (HTGR) of low and medium capacity with the intrinsic property of safety. HTGR of low (about 200-250 MW(th) in a steel vessel), medium (about 500 MW(th) in a steel-concrete vessel) and high (about 1000-2500 MW(th) in a prestressed concrete vessel) are now designed and studied in the country. At outlet helium temperature of 920-1020 K it is possible to create steam turbine installations producing both

  4. The choice of equipment mix and parameters for HTGR-based nuclear cogeneration plants

    International Nuclear Information System (INIS)

    Malevski, A.L.; Stoliarevski, A.Ya.; Vladimirov, V.T.; Larin, E.A.; Lesnykh, V.V.; Naumov, Yu.V.; Fedotov, I.L.

    1990-01-01

    Improvement of heat and electricity supply systems based on cogeneration is one of the high-priority problems in energy development of the USSR. Fossil fuel consumption for heat supply exceeds now its use for electricity production and amounts to about 30% of the total demands. District heating provides about 80 million t.c.e. of energy resources conserved annually and meets about 50% of heat consumption of the country, including about 30% due to cogeneration. The share of natural gas and liquid fuel in the fuel consumption for district heating is about 70%. The analysis of heat consumption dynamics in individual regions and industrial-urban agglomerations shows the necessity of constructing cogeneration plants with the total capacity of about 60 million kW till the year 2000. However, their construction causes some serious problems. The most important of them are provision of environmentally clean fuels for cogeneration plants and provision of clear air. The limited reserves of oil and natural gas and the growing expenditures on their production require more intensive introduction of nuclear energy in the national energy balance. Possible use of nuclear energy based on light-water reactors for substitution of deficient hydrocarbon fuels is limited by the physical, technical and economic factors and requirements of safety. Further development of nuclear energy in the USSR can be realized on a new technological base with construction of domestic reactors of increased and ultimate safety. The most promising reactors under design are high-temperature gas-cooled reactors (HTGR) of low and medium capacity with the intrinsic property of safety. HTGR of low (about 200-250 MW(th) in a steel vessel), medium (about 500 MW(th) in a steel-concrete vessel) and high (about 1000-2500 MW(th) in a prestressed concrete vessel) are now designed and studied in the country. At outlet helium temperature of 920-1020 K it is possible to create steam turbine installations producing both

  5. The study of two, three and four dimensional nonlinear dynamics of nuclear fission reactors and effective parameters on its behaviour

    International Nuclear Information System (INIS)

    Tajik, M.; Ghasemizad, A.

    2008-01-01

    In this research, new physical fission reactor parameters which have very sensitive effects on the qualitative behavior of a reactor, are introduced. Therefore, the two, the nonlinear dynamics of two, three and four dimensional, considering almost the effective parameters are formulated for describing nuclear fission reactor systems. Using both analytical and numerical methods, the stability and instability of the given dynamical equations and the conditions of stability are studied in these systems. We have shown that the two parameters of the mean energy residence time in fuel and coolant and also their ratios have the most qualitative effects on the dynamical behaviour of a typical nuclear fission reactor. Increasing or decreasing of these parameters from a captain limit can lead to stability or un stability in a given system

  6. Scholarship for Nuclear Communications and Methods for Evaluation of Nuclear Project Acceptability

    Energy Technology Data Exchange (ETDEWEB)

    Golay, Michael [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    2016-10-30

    This project aims to go beyond effective communication in understanding how to design nuclear enterprise projects that will gain stakeholder acceptability. Much of what we are studying is generally applicable to controversial projects, and we expect our results to be of broad value beyond the nuclear arena. Acceptability is more than effective communication; it also requires varying degrees of engagement with a disparate number of stakeholder groups. In the nuclear enterprise, previous attempts have been well designed physically (i.e., technologically sound), but have floundered by being insensitive concerning acceptance. Though effective communication is a necessary, but insufficient, condition for such success, there is a lack of scholarship regarding how to gain stakeholder acceptance for new controversial projects, including nuclear ones. Our work is building a model for use in assessing the performance of a project in the area of acceptability. In the nuclear-social nexus, gaining acceptance requires a clear understanding of factors regarded as being important by the many stakeholders that are common to new nuclear project (many of whom hold an effective veto power). Projects tend to become socially controversial when public beliefs, expert opinion and decision-maker understanding are misaligned. As such, stakeholder acceptance is hypothesized as both an ongoing process and an initial project design parameter comprised of complex, social, cognitive and technical components. Controversial projects may be defined as aspects of modern technologies that some people question, or are cautious about. They could range from genetic modifications, biological hazards, effects of chemical agents, nuclear radiation or hydraulic fracturing operations. We intend that our work will result in a model likely to be valuable for refining project design and implementation to increase the knowledge needed for successful management of stakeholder relationships.

  7. Technical and economic evaluation of nuclear seawater desalination systems

    International Nuclear Information System (INIS)

    Grechko, A.G.; Romenkov, A.A.; Shishkin, V.A.

    1998-01-01

    The IAEA Cogeneration/Desalination Cost Model spreadsheets were used for the economic evaluation of sea water desalination plants coupled with small and medium size nuclear reactors developed in RDIPE. The results of calculations have shown that the cost of potable water is equal to or even below 1$/m 3 . This is very close to similar indices of the best fossil driven desalination plants. For remote and difficult-to-access regions, where the transportation share contributes significantly to the product water cost at fossil plants, the nuclear power sources of these reactor types are cost-efficient and can successfully compete with fossil power sources. (author)

  8. Systematic safety evaluation of old nuclear power plants

    International Nuclear Information System (INIS)

    Dredemis, G.; Fourest, B.

    1984-01-01

    The French safety authorities have undertaken a systematic evaluation of the safety of old nuclear power plants. Apart from a complete revision of safety documents (safety analysis report, general operating rules, incident and accident procedures, internal emergency plan, quality organisation manual), this examination consisted of analysing the operating experience of systems frequently challenged and a systematic examination of the safety-related systems. This paper is based on an exercise at the Ardennes Nuclear Power Plant which has been in operation for 15 years. This paper also summarizes the main surveys and modifications relating to this power plant. (orig.)

  9. Nuclear logging apparatus and MWD-equipment for formation evaluation

    International Nuclear Information System (INIS)

    Perry, C.A.; Daigle, G.A.; Rountree, S.P.; Talmadge, G.; Grunbeck, J.; Wassell, M

    1998-01-01

    An apparatus for nuclear logging is presented. In accordance with the present invention, nuclear detectors and electronic components are all mounted in chambers within the sub wall with covers being removably attached to the chambers. A single bus for delivering both power and signals extends through the sub wall between either end of the tool. This bus terminates at a modular ring connector positioned on each tool end. This tool construction (including sub wall mounted sensors and electronics, single power and signal bus, and ring connectors) is also well suited for other formation evaluation tools used in measurement-while-drilling applications. 28 refs

  10. Sensitivity analysis of critical experiments with evaluated nuclear data libraries

    International Nuclear Information System (INIS)

    Fujiwara, D.; Kosaka, S.

    2008-01-01

    Criticality benchmark testing was performed with evaluated nuclear data libraries for thermal, low-enriched uranium fuel rod applications. C/E values for k eff were calculated with the continuous-energy Monte Carlo code MVP2 and its libraries generated from Endf/B-VI.8, Endf/B-VII.0, JENDL-3.3 and JEFF-3.1. Subsequently, the observed k eff discrepancies between libraries were decomposed to specify the source of difference in the nuclear data libraries using sensitivity analysis technique. The obtained sensitivity profiles are also utilized to estimate the adequacy of cold critical experiments to the boiling water reactor under hot operating condition. (authors)

  11. Technical evaluation of bids for nuclear power stations

    International Nuclear Information System (INIS)

    Zijl, N.A. van

    1976-01-01

    A bid evaluation method is described which, it is claimed, facilitates a distinct and objective judgement of bids, taking into account the importance of the components, systems, and technical aspects evaluated with regard to the operation and safety of a nuclear power station. The evaluation basically consists of a cost assessment of the scope of supply deviations and a numerical evaluation of the technical design, the latter being a particularly novel feature of the method. The logic applied in both processes is shown. Main evaluation criteria which are applied for most components and systems are given as reliability, function and performance, safety, operation and maintenance, and materials. The judgements given to these evaluation criteria form the basis of the numerical bid evaluation described, which is carried out with the aid of computer programs. (U.K.)

  12. Japanese evaluated nuclear data library version 3, JENDL-3

    International Nuclear Information System (INIS)

    Asami, Tetsuo; Igarashi, Shun-ichi; Ihara, Hitoshi

    1989-01-01

    The third version of Japanese Evaluated Nuclear Data Library, JENDL-3, has recently been compiled and issued. The major features of JENDL-3 are that it covers a much larger number of nuclides than the previous versions, that evaluation is made over the all energy regions from 10 -5 eV to 20 MeV using proper nuclear theories for each of the energy regions, and that it contains data on gamma ray generation. The present report first gives an outline of JENDL-3, and then describes the evaluation of nuclear data covering light nuclides, nuclides in structural materials, fission product nuclides, major actinide nuclides, transplutonium nuclides, and gamma ray generation. The applicability of JENDL-3 is examined through a variety of bench mark tests covering the fast reactor, thermal neutron reactor, shielding, neutronics of nuclear fusion reactor, dosimetry, and gamma ray generation data. The report also describes a library for calculation of decay heat, which has close relations with JENDL-3. It has been demonstrated that the experimental data given in this library are very reliable with high reproducibility. Additional activities planned for the future are also outlined briefly. (N.K.)

  13. Generation of CR mammographic image for evaluation quality parameters

    International Nuclear Information System (INIS)

    Flores, Mabel B.; Mourao, Arnaldo P.; Centro Federal de Educacao Tecnologica de Minas Gerais

    2017-01-01

    Currently, among the diseases most feared by women, breast cancer ranks first in the world with an incidence of more than 1.6 million cases and a mortality of more than 521.9 thousand cases by year, which makes this disease the type of cancer with higher incidence and mortality compared to the other types of cancer that mainly affect the female gender, without considering non-melanoma skin cancer. In Brazil, more than 14.4 thousand deaths were registered in 2013 and more than 57 thousand new cases were estimated for 2016. The use of computerized radiography (CR) for the generation of mammographic digital images is widely used in Brazil for the screening of breast cancer. The aim of this investigation is to study the variation of CR plate response to exposure to X-ray beams in a mammography unit. Two CR plates from different manufacturers and a compressed breast phantom containing calcium carbonate structures of different sizes simulating calcifications were used for this study. An X-ray beam generated by 30 kV was selected to realize successive exposures of each plate by performing a time variation of 0.5 to 3.5 s, obtaining the raw images. The acquired images were evaluated with the ImageJ software to determine the saturation time of the plates when exposed to X-ray beams and the qualitative resolution of each plate. The plates were found to saturate at different times when exposed under the same conditions to X-ray beams. By means of the images acquired with the breast phantom, it was possible to observe only structures of calcium carbonate with sizes greater than 177 μm. (author)

  14. Evaluation of Anthropometric and Metabolic Parameters in Obstructive Sleep Apnea

    Directory of Open Access Journals (Sweden)

    Yaşar Yildirim

    2015-01-01

    Full Text Available Aims. Sleep disorders have recently become a significant public health problem worldwide and have deleterious health consequences. Obstructive sleep apnea (OSA is the most common type of sleep-related breathing disorders. We aimed to evaluate anthropometric measurements, glucose metabolism, and cortisol levels in patients with obstructive sleep apnea (OSA. Materials and Methods. A total of 50 patients with a body mass index ≥30 and major OSA symptoms were included in this study. Anthropometric measurements of the patients were recorded and blood samples were drawn for laboratory analysis. A 24-hour urine sample was also collected from each subject for measurement of 24-hour cortisol excretion. Patients were divided equally into 2 groups according to polysomnography results: control group with an apnea-hypopnea index (AHI <5 (n=25 and OSA group with an AHI ≥5 (n=25. Results. Neck and waist circumference, fasting plasma glucose, HbA1c, late-night serum cortisol, morning serum cortisol after 1 mg dexamethasone suppression test, and 24-hour urinary cortisol levels were significantly higher in OSA patients compared to control subjects. Newly diagnosed DM was more frequent in patients with OSA than control subjects (32% versus 8%, p=0.034. There was a significant positive correlation between AHI and neck circumference, glucose, and late-night serum cortisol. Conclusions. Our study indicates that increased waist and neck circumferences constitute a risk for OSA regardless of obesity status. In addition, OSA has adverse effects on endocrine function and glucose metabolism.

  15. Generation of CR mammographic image for evaluation quality parameters

    Energy Technology Data Exchange (ETDEWEB)

    Flores, Mabel B.; Mourao, Arnaldo P., E-mail: mbustos@ufmg.br, E-mail: apratabhz@gmail.com [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Centro Federal de Educacao Tecnologica de Minas Gerais (CEFET-MG), Belo Horizonte, MG (Brazil). Centro de Engenharia Politecnica

    2017-11-01

    Currently, among the diseases most feared by women, breast cancer ranks first in the world with an incidence of more than 1.6 million cases and a mortality of more than 521.9 thousand cases by year, which makes this disease the type of cancer with higher incidence and mortality compared to the other types of cancer that mainly affect the female gender, without considering non-melanoma skin cancer. In Brazil, more than 14.4 thousand deaths were registered in 2013 and more than 57 thousand new cases were estimated for 2016. The use of computerized radiography (CR) for the generation of mammographic digital images is widely used in Brazil for the screening of breast cancer. The aim of this investigation is to study the variation of CR plate response to exposure to X-ray beams in a mammography unit. Two CR plates from different manufacturers and a compressed breast phantom containing calcium carbonate structures of different sizes simulating calcifications were used for this study. An X-ray beam generated by 30 kV was selected to realize successive exposures of each plate by performing a time variation of 0.5 to 3.5 s, obtaining the raw images. The acquired images were evaluated with the ImageJ software to determine the saturation time of the plates when exposed to X-ray beams and the qualitative resolution of each plate. The plates were found to saturate at different times when exposed under the same conditions to X-ray beams. By means of the images acquired with the breast phantom, it was possible to observe only structures of calcium carbonate with sizes greater than 177 μm. (author)

  16. Design and evaluation of physical protection systems of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    An, Jin Soo; Lee, Hyun Chul; Hwang, In Koo; Kwack, Eun Ho; Choi, Yung Myung

    2001-06-01

    Nuclear material and safety equipment of nuclear facilities are required to be protected against any kind of theft or sabotage. Physical protection is one of the measures to prevent such illegally potential threats for public security. It should cover all the cases of use, storage, and transportation of nuclear material. A physical protection system of a facility consists of exterior intrusion sensors, interior intrusion sensors, an alarm assessment and communication system, entry control systems, access delay equipment, etc. The design of an effective physical protection system requires a comprehensive approach in which the designers define the objective of the system, establish an initial design, and evaluate the proposed design. The evaluation results are used to determine whether or not the initial design should be modified and improved. Some modelling techniques are commonly used to analyse and evaluate the performance of a physical protection system. Korea Atomic Energy Research Institute(KAERI) has developed a prototype of software as a part of a full computer model for effectiveness evaluation for physical protection systems. The input data elements for the prototype, contain the type of adversary, tactics, protection equipment, and the attributes of each protection component. This report contains the functional and structural requirements defined in the development of the evaluation computer model.

  17. Preparation of data for criticality safety evaluation of nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Okuno, Hiroshi; Suyama, Kenya; Yoshiyama, Hiroshi; Tonoike, Kotaro; Miyoshi, Yoshinori

    2005-01-01

    Nuclear Criticality Safety Handbook/Data Collection, Version 2 was submitted to the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan as a contract report. In this presentation paper, its outline and related recent works are presented. After an introduction in Chapter 1, useful information to obtain the atomic number densities was collected in Chapter 2. The nuclear characteristic parameters for 11 nuclear fuels were provided in Chapter 3, and subcriticality judgment graphs were given in Chapter 4. The estimated critical and estimated lower-limit critical values were supplied for the 11 nuclear fuels as results of calculations by using the Japanese Evaluated Nuclear Data Library, JENDL-3.2, and the continuous energy Monte Carlo neutron transport code MVP in Chapter 5. The results of benchmark calculations based on the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook were summarized into six fuel categories in Chapter 6. As for recent works, subcriticality judgment graphs for U-SiO 2 and Pu-SiO 2 were obtained. Benchmark calculations were made with the combination of the latest version of the library JENDL-3.3 and MVP code for a series of STACY experiments and the estimated critical and estimated lower-limit critical values of 10 wt%-enriched uranium nitrate solutions were calculated. (author)

  18. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Chadwick, M B; Oblozinsky, P; Herman, M; Greene, N M; McKnight, R D; Smith, D L; Young, P G; MacFarlane, R E; Hale, G M; Haight, R C; Frankle, S; Kahler, A C; Kawano, T; Little, R C; Madland, D G; Moller, P; Mosteller, R; Page, P; Talou, P; Trellue, H; White, M; Wilson, W B; Arcilla, R; Dunford, C L; Mughabghab, S F; Pritychenko, B; Rochman, D; Sonzogni, A A; Lubitz, C; Trumbull, T H; Weinman, J; Brown, D; Cullen, D E; Heinrichs, D; McNabb, D; Derrien, H; Dunn, M; Larson, N M; Leal, L C; Carlson, A D; Block, R C; Briggs, B; Cheng, E; Huria, H; Kozier, K; Courcelle, A; Pronyaev, V; der Marck, S

    2006-10-02

    We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, {sup 6}Li, {sup 10}B, Au and for {sup 235,238}U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases. The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The {sup 238}U, {sup 208}Pb, and {sup 9}Be reflector

  19. Update neutron nuclear data evaluation for 236,238Np

    International Nuclear Information System (INIS)

    Chen, Guochang; Wang, Jimin; Yu, Baosheng; Cao, Wentian; Tang, Guo-you

    2015-01-01

    The nuclear data with high accuracy for actinides play an important role in nuclear technology applications, including reactor design and operation, fuel cycle, estimation of the amount of minor actinides (MAs) in high burnup reactors and to research to transmute the MAs to short half-lived nuclides or stable ones. The nuclides of 236 Np are generated via the α-decay of 240 Am or 237 Np(n, 2n) and 237 Np(d, t) reactions. And the nuclides of 238 Np are generated via the α-decay of 242 Am or 237 Np(n, γ) and 237 Np(d, p) reactions. In the present work, according to the systematic trend of the total cross section and elastic cross section etc. of different Np isotopes, and based on the neutron optical model parameters (OMP) of 237 Np, a new set of neutron optical model parameters were obtained for 236,238 Np. Based on the new set OMP and the systematic trend of the cross sections of different Np isotopes, a full set of 236,238 Np neutron nuclear data has been updated and improved by theoretical calculation. The present result has significant improvements over the data in CENDL-3.1

  20. Parameters of Dismantling Techniques Related to Costs for Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Jeong, Kwanseong; Moon, Jeikwon; Choi, Byungseon

    2012-01-01

    Reliable cost estimating is one of the most important elements of decommissioning operation. Reliable cost estimating is one of the most important elements of decommissioning planning. Alternative technologies may be evaluated and compared on their efficiency and effectiveness, and measured against a baseline cost as to the feasibility and benefit derived from the technology. This principle ensures that the cost consideration is economically sound and practical for funding. This paper provides a list with basic review of cutting and dismantling techniques, including some typical characteristics if available, as well as aspects of implementation, parameters of cutting and dismantling techniques in decommissioning costing. This paper gives an overview of the principles of the unit factor approach and its implementation in costing in relation to dismantling activities. In general, proper evaluation of decommissioning costs is important for following issues and relevant measures for achieving the listed aspects are: · Selection of a decommissioning strategy and activities: several decommissioning options should be evaluated: · Support to a cost-benefit analysis to ensure that the principle of optimization and reasonably practicable measures are applied: the extent of evaluated decommissioning options should cover all possible scenarios for dismantling activities; · Estimate of required financial resources for the selected strategy: the selected option should involve the dismantling activities in a structure and extent relevant to real procedure of dismantling activities; · Preparation of the project schedule, workforce requirements and phased funding needs: dismantling activities should be structured according to the tasks of the decommissioning schedule; · Definition of measures for proper management and maintenance of resources for safe and timely decommissioning: the time distribution and safety related parameters of dismantling activities should be known

  1. performance-based approach to design and evaluation of nuclear security systems for Brazilian nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Tavares, Renato L. A.; Filho, Josélio S. M., E-mail: renato.tavares@cnen.gov.br, E-mail: joselio@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear. Divisão de Normas e Segurança Física; Fontes, Gladson S.; Fiel, J.C.B., E-mail: gsfontes@hotmail.com, E-mail: fiel@ime.eb.br [Instituto Militar de Engenharia (SE-7/IME), Rio de Janeiro, RJ (Brazil). Seção de Engenharia Nuclear

    2017-07-01

    This study presents an application of a performance-based approach to definition of requirements, design and evaluation of physical protection systems for nuclear facilities. Such approach considers a probabilistic analysis of the threat, equipment, systems and response forces used to prevent, dissuade and detain malicious acts against the integrity of facilities and the nuclear materials inside them. Nowadays, in the context of Brazilian nuclear facilities licensing, a mostly prescriptive approach is adopted, which despite having advantages such as simplified inspections and homogeneous regulatory requisites amid different fuel cycle facility types, does not consider evolution, dynamism and capacities of external or internal threats to facilities and to Brazilian Nuclear Program itself, neither provides metrics to evaluate system performance facing such threats. In order to preserve actual plans and systems confidentiality, a facility hypothetical model is created, including a research reactor and a waste storage facility. It is expected that the methodology and results obtained in this study serve in the future as a basis to Brazilian nuclear operators, in elaboration process of their Physical Protection Plans, which must comply with future regulation CNEN-NN 2.01, a revision of CNEN-NE 2.01, once that regulation will include performance requisites. (author)

  2. performance-based approach to design and evaluation of nuclear security systems for Brazilian nuclear facilities

    International Nuclear Information System (INIS)

    Tavares, Renato L. A.; Filho, Josélio S. M.; Fontes, Gladson S.; Fiel, J.C.B.

    2017-01-01

    This study presents an application of a performance-based approach to definition of requirements, design and evaluation of physical protection systems for nuclear facilities. Such approach considers a probabilistic analysis of the threat, equipment, systems and response forces used to prevent, dissuade and detain malicious acts against the integrity of facilities and the nuclear materials inside them. Nowadays, in the context of Brazilian nuclear facilities licensing, a mostly prescriptive approach is adopted, which despite having advantages such as simplified inspections and homogeneous regulatory requisites amid different fuel cycle facility types, does not consider evolution, dynamism and capacities of external or internal threats to facilities and to Brazilian Nuclear Program itself, neither provides metrics to evaluate system performance facing such threats. In order to preserve actual plans and systems confidentiality, a facility hypothetical model is created, including a research reactor and a waste storage facility. It is expected that the methodology and results obtained in this study serve in the future as a basis to Brazilian nuclear operators, in elaboration process of their Physical Protection Plans, which must comply with future regulation CNEN-NN 2.01, a revision of CNEN-NE 2.01, once that regulation will include performance requisites. (author)

  3. Evaluation of nuclear data of {sup 244}Pu and {sup 237}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo; Konshin, V.A. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1995-10-01

    The evaluation of nuclear data for {sup 244}Pu and {sup 237}Pu was made in the neutron energy region from 10{sup -5} eV to 20 MeV. For the both nuclides, the total, elastic and inelastic scattering, fission, capture, (n,2n) and (n,3n) reaction cross sections were evaluated on the basis of theoretical calculation. The resonance parameters were given for {sup 244}Pu. The angular and energy distributions of secondary neutrons were also estimated for the both nuclides. The results were compiled in the ENDF-5 format and will be adopted in JENDL Actinoid File. (author).

  4. Monte Carlo code Serpent calculation of the parameters of the stationary nuclear fission wave

    Directory of Open Access Journals (Sweden)

    V. M. Khotyayintsev

    2017-12-01

    Full Text Available n this work, propagation of the stationary nuclear fission wave was simulated for series of fixed power values using Monte Carlo code Serpent. The wave moved in the axial direction in 5 m long cylindrical core of fast reactor with pure 238U raw fuel. Stationary wave mode arises some period later after the wave ignition and lasts sufficiently long to determine kef with high enough accuracy. The velocity characteristic of the reactor was determined as the dependence of the wave velocity on the neutron multiplication factor. As we have recently shown within a one-group diffusion description, the velocity characteristic is two-valued due to the effect of concentration mechanisms, while thermal feedback affects it only quantitatively. The shape and parameters of the velocity characteristic critically affect feasibility of the reactor design since stationary wave solutions of the lower branch are unstable and do not correspond to any real waves in self-regulated reactor, like CANDLE. In this work calculations were performed without taking into account thermal feedback. They confirm that theoretical dependence correctly describes the shape of the velocity characteristic calculated using the results of the Serpent modeling.

  5. Nuclear magnetism of liquid 3He: new determination of the Landau parameter F0a

    International Nuclear Information System (INIS)

    Goudon, V.

    2006-10-01

    He 3 is a liquid Fermi model, isotropic, with an attainable Fermi temperature and the interaction between atoms can be controlled by changing the pressure of the liquid. In this document, we present accurate NMR measurements of the nuclear magnetic susceptibility of liquid He 3 as a function of temperature and pressure. The emphasis has been placed on reliable thermometry and on He 3 pressure measurements directly in the cell to increase the measuring range until solidification, and an accurate characterization of the NMR spectrometer. Our measurements give an effective Fermi temperature 5% lower than former results. The Landau parameter F 0 a depends on the effective mass, which is determined by specific heat measurements, and consequently on the temperature scale. The re-analysis of the specific heat measurements with the PLTS-2000 temperature scale yields an effective mass increase of 4.5%. In this document, F 0 a is determined for 2 temperature scales (PLTS-2000 and Greywall). Contrarily to former measurements, the F 0 a density dependence does not show any saturation at high pressures. (author)

  6. Determination of a test section parameters for Iris nuclear reactor pressurizer

    International Nuclear Information System (INIS)

    Silva, Mario A.B. da; Lira, Carlos A.B. de O.

    2009-01-01

    An integral, modular and medium size nuclear reactor, known as IRIS, is being developed by Westinghouse and by research centers. IRIS is characterized by having most of its components inside the pressure vessel, eliminating the probability of accidents. Due to its integral configuration, there is no spray system for boron homogenization, which may cause power transients. Thus, boron mixing must be investigated. The aim of this paper is to establish the conditions under which a test section has to be built for boron dispersion analysis inside IRIS reactor pressurizer. Through Fractional Scaling Analysis, which is a new methodology of similarity, the main parameters for a test section are obtained. By combining Fractional Scaling Analysis with local scaling for the densimetric Froude number and a previously established volumetric scale factor, the values of recirculation orifices, inlet water temperature, time scale factor and recirculation flow for the test section (model) are determined so that boron distribution is well represented in IRIS reactor pressurizer (prototype). Analytical solutions were used to validate the adopted methodology and when the results simulated in the model are compared to those that characterize the prototype, the agreement for both systems is absolute. The thermal power also influences boron distribution inside the test section. This power is determined by condensation laws in the vapor region and by suitable correlations for free convection. The fractions for rising inlet recirculation water enthalpy and vapor formation are also considered. (author)

  7. Nuclear data standards - International Evaluation Co-operation volume 7

    International Nuclear Information System (INIS)

    Carlson, A.D.; Shibata, K.; Vonach, H.; Hambsch, F.J.; Chen, Z.; Hofmann, H.M.; Oh, S.Y.; Badikov, S.A.; Gai, E.V.; Pronyaev, V.G.; Smith, D.L.; Hale, G.M.; Kawano, T.; Larson, N.M.

    2006-01-01

    A Working Party on International Evaluation Co-operation was established under the sponsorship of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data evaluations, validation and related topics. Its aim is also to provide a framework for co-operative activities between members of the major nuclear data evaluation projects. This includes the possible exchange of scientists in order to encourage co-operation. Requirements for experimental data resulting from this activity are compiled. The working party determines common criteria for evaluated nuclear data files with a view to assessing and improving the quality and completeness of evaluated data. The parties to the project are: ENDF (United States), JEFF/EFF (NEA Data Bank member countries) and JENDL (Japan). Co-operation with evaluation projects of non-OECD countries is organised through the Nuclear Data Section of the International Atomic Energy Agency (IAEA). This report was issued by Subgroup 7, which was in charge of producing new evaluated neutron cross-section standards. When starting the project, there was a general consensus on the need to update these standards, as significant improvements had been made to the experimental database since 1991 when the last evaluation of these standards was performed. The present work was accomplished through efficient collaboration between a task force of the US Cross-section Evaluation Working Group (CSEWG), a Co-ordinated Research Project (CRP) of the International Atomic Energy Agency (IAEA) and Subgroup 7 of the Working Party on International Evaluation Co-operation (WPEC) of the NEA Nuclear Science Committee. Work is reported on the results of an international effort to evaluate the neutron cross-section standards. The evaluations include the H(n,n), 6 Li(n,t), 10 B(n,α), 10 B(n,α1γ), 197 Au(n,γ), 235 U(n,f) and 238 U(n,f) standard reactions. Evaluations were also produced for the non-standard 238 U(n,γ) and 239 Pu

  8. EMI Evaluation on Wireless Computer Devices in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Jae Ki; JI Yeong Hwa; Sung, Chan Ho

    2011-01-01

    Wireless computer devices, for example, mice and keyboards are widely used in various industries. However, I and C (instrumentation and control) equipment in nuclear power plants are very susceptible to the EMI (Electro-magnetic interference) and there are concerns regarding EMI induced transient caused by wireless computer devices which emit electromagnetic waves for communication. In this paper, industrial practices and nuclear related international standards are investigated to verify requirements of wireless devices. In addition, actual measurement and evaluation for the intensity of EMI of some commercially available wireless devices is performed to verify their compatibility in terms of EMI. Finally we suggest an appropriate method of using wireless computer devices in nuclear power plant control rooms for better office circumstances of operators

  9. Systematic evaluation of nuclear operator team skills training

    International Nuclear Information System (INIS)

    Harrington, D.K.; Kello, J.E.

    1991-01-01

    In recent years, the nuclear industry has increasingly recognized with the technical training given its control room operators. As yet, however, little has been done to determine the actual effectiveness of such nontechnical training. Thus, the questions of how team training should be carried out for maximum impact on the safety and efficiency of control room operation and just what the benefits of such training might be remain open. We are in the early stages of establishing a systematic evaluation process that will help nuclear utilities assess the effectiveness of their existing team skills training programs for control room operators. Research focuses on defining the specific behavioral and attitudinal objectives of team skills training. Simply put, what does good practice look like and sound like in the control room environment? What specific behaviors and attitudes should the training be directed toward? Obviously, the answers to the questions have clear implications for the design of nuclear team skills training programs

  10. Evaluation of masonry wall design at nuclear power plants

    International Nuclear Information System (INIS)

    Con, V.N.; Subramonian, N.; Chokshi, N.

    1983-01-01

    The structural integrity of safety-related masonry walls in operating nuclear power plants may not be maintained when subjected to certain loads and load combinations. The paper presents some findings based upon the review of the design and analysis procedures used by the licensees in the reevaluation of safety-related masonry walls. The design criteria developed by the Structural Engineering Branch (SEB) of the United States Nuclear Regulatory Commission (NRC) along with other standard codes such as the Uniform Building Code, ACI 531-79, ATC 3-06, and NCMA were used as guidance in evaluating the design criteria developed by the licensees. The paper deals with the following subject areas: loads and load combinations, allowable stresses, analytical procedures, and modification methods. The paper concludes that, in general, the masonry walls in nuclear power plants comply with the working stress design requirements. In some cases, certain nonlinear analysis methods were used. The applicability of these methods is discussed. (orig.)

  11. Evaluation of Perry Nuclear Power Plant Unit 1 technical specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-11-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Perry Nuclear Power Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Perry T/S. Several discrepancies were identified and subsequently resolved through telephone conversations with the staff reviewer and the utility representative. Pending completion of the resolutions noted in Parts 3 and 4 of this report, the Perry Nuclear Power Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  12. Evaluation of Watts Bar Nuclear Plant Unit 1 Technical Specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-08-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Watts Bar Nuclear Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumption of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Watts Bar T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Watts Bar Nuclear Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  13. Evaluation of Shoreham Nuclear Power Station, Unit 1 technical specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-08-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Shoreham Nuclear Power Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumptions of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Shoreham T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Shoreham Nuclear Power Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  14. Evaluation of neutron nuclear data for 241Am and 243Am

    International Nuclear Information System (INIS)

    Kikuchi, Yasuyuki

    1982-08-01

    Neutron nuclear data of 241 Am and 243 Am were evaluated for JENDL-2. Evaluated quantities are the total, elastic and inelastic scattering, fission, capture, (n,2n), (n,3n) and (n,4n) reaction cross sections, the resolved and unresolved resonance parameters, the angular or energy distribution of the emitted neutrons, and the average number of neutrons emitted per fission. The fission cross section was evaluated on the basis of newly measured data, and lower values than JENDL-1 were given in the subthreshold energy region. The reliability of the calculation parameters are also much improved, because experimental data became available for the total and capture cross sections of 241 Am in the high energy region. (author)

  15. Prototype of evaluation guidance system in Integrated Nuclear Data Evaluation System

    International Nuclear Information System (INIS)

    Fukahori, T.; Nakagawa, T.

    1992-01-01

    Integrated Nuclear Data Evaluation System (INDES) is being developed to keep experiences of nuclear data evaluation for JENDL-3 and to support new evaluations. One of the INDES functions is to set up input data of theoretical calculation codes automatically. In order to use INDES effectively, a prototype of nuclear data evaluation guidance system (E.T.; Evaluation Tutor) was made to help users in selecting a set of suitable theoretical calculation codes by applying knowledge engineering technology. E.T. consists of an inference engine, frames, a rule-base, two example-bases and calculating modules of certainty factors. The inference engine and the calculating modules are written in FORTRAN77. (author)

  16. Evaluation of Haddam Neck (Connecticut Yankee) Nuclear Power Plant, environmental impact prediction, based on monitoring programs

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Mahaffey, J.A.; Waton, D.G.

    1976-12-01

    A study was undertaken by the U.S. Nuclear Regulatory Commission (NRC) to evaluate the nonradiological environmental data obtained from three nuclear power plants operating for a period of one year or longer. The document presented reports the second of three nuclear power plants to be evaluated in detail by Battelle, Pacific Northwest Laboratories. Haddam Neck (Connecticut Yankee) Nuclear Power Plant nonradiological monitoring data were assessed to determine their effectiveness in the measurement of environmental impacts. Efforts were made to determine if: (1) monitoring programs, as designed, can detect environmental impacts, (2) appropriate statistical analyses were performed and if they were sensitive enough to detect impacts, (3) predicted impacts could be verified by monitoring programs, and (4) monitoring programs satisfied the requirements of the Environmental Technical Specifications. Both preoperational and operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the methods used to measure ecological, chemical, and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data sets were available. From this type of analysis, deficiencies in both preoperational and operational monitoring programs may be identified and provide a basis for suggested improvement

  17. Evaluation of mini super computers for nuclear design applications

    International Nuclear Information System (INIS)

    Altomare, S.; Baradari, F.

    1987-01-01

    The evolution of the mini super computers will force changes from the current environment of performing nuclear design calculations on mainframe computers (such as a CRAY) to mini super computers. This change will come about for a number of reasons. First, the mini super computers currently available in the marketplace offer the power and speed comparable to mainframes and can provide the capability to support highly computer intensive calculations. Second, the equipment is physically smaller and can easily be installed and operated without extensive investments in facilities and operations support. Third, the computer capacity can be acquired with as much needed memory, disk, and tape capacity as may be needed. Another reasons is that the performance/cost ratio has increased drastically as hardware costs have decreased. A study was conducted at the Westinghouse Commercial Nuclear Fuel Division (CNFD) to evaluate the mini super computers for use in nuclear core design. As a result of this evaluation, Westinghouse CNFD is offering a combined hardware/software technology transfer package for core design. This package provides the utility designer with a totally dedicated mini super computer comparable in speed to the CRAY 1S with sufficient capacity for a sizable design group to perform the engineering activities related to nuclear core design and operations support. This also assures the utility of being totally compatible with the CNFD design codes, thus assuring total update compatibility

  18. A methodology for nuclear power plant operational events evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Jeferson, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CGRC/CNEN), Rio de janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo de Combustivel; Costa, Sergio Dias, E-mail: sergiodiascosta@hotmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    Operational events are normal occurrences in industrial plants and in nuclear power plants. The evaluation of operational events gains importance when it comes specifically to nuclear power plants due to the proportions that the impact and the consequences of these events may cause to the installation itself, their workers, the external area of the nuclear installation, the environment and to the public in general. These consequences, for the operation of these facilities can range from very little, until the consequences that lead to accidents and can cause significant impacts. Operational events may be associated or have influence in many fields of knowledge, such as operation, maintenance, engineering, Radiological Protection, physical protection, chemistry, Human or Organizational Factors and external events, among others. The accident at the Fukushima Daichi nuclear power plant, shows the importance of exhausting all the studies concerning operational events in order to improve the operational safety of nuclear plants, considering all the causes and possible consequences. In this context, the evaluation of operational events discipline emerges as an important and relevant tool to contribute to the maintenance and/or improvement of the operational safety of nuclear installations. Not without reason the nuclear industry actively participates in programs of exchange of operational experience, where relevant events are thoroughly evaluated and discussed in specific forums, such as power plant operators, regulators and/or joint technical meetings, always with the purpose to prevent, minimize or mitigate its consequences. Any evaluation of operational events passes necessarily by an in-depth study of the circumstances of the event, culminating with the identification of your cause and proposition of corrective actions to prevent recurrence of similar events. Additionally, the events should not be studied individually, but evaluated within a temporal context in order

  19. A methodology for nuclear power plant operational events evaluation

    International Nuclear Information System (INIS)

    Araujo, Jeferson

    2015-01-01

    Operational events are normal occurrences in industrial plants and in nuclear power plants. The evaluation of operational events gains importance when it comes specifically to nuclear power plants due to the proportions that the impact and the consequences of these events may cause to the installation itself, their workers, the external area of the nuclear installation, the environment and to the public in general. These consequences, for the operation of these facilities can range from very little, until the consequences that lead to accidents and can cause significant impacts. Operational events may be associated or have influence in many fields of knowledge, such as operation, maintenance, engineering, Radiological Protection, physical protection, chemistry, Human or Organizational Factors and external events, among others. The accident at the Fukushima Daichi nuclear power plant, shows the importance of exhausting all the studies concerning operational events in order to improve the operational safety of nuclear plants, considering all the causes and possible consequences. In this context, the evaluation of operational events discipline emerges as an important and relevant tool to contribute to the maintenance and/or improvement of the operational safety of nuclear installations. Not without reason the nuclear industry actively participates in programs of exchange of operational experience, where relevant events are thoroughly evaluated and discussed in specific forums, such as power plant operators, regulators and/or joint technical meetings, always with the purpose to prevent, minimize or mitigate its consequences. Any evaluation of operational events passes necessarily by an in-depth study of the circumstances of the event, culminating with the identification of your cause and proposition of corrective actions to prevent recurrence of similar events. Additionally, the events should not be studied individually, but evaluated within a temporal context in order

  20. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

    International Nuclear Information System (INIS)

    Chadwick, M.B.; Oblozinsky, P.; Herman, M.

    2006-01-01

    We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes, based on experimental data and theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, 6 Li, 10 B, Au and for 235,238 U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced evaluations up to 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; (10) New methods for uncertainties and covariances, together with covariance evaluations for some sample cases; and (11) New actinide fission energy deposition. The paper provides an overview of this library, consisting of 14 sublibraries in the same ENDF-6 format as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched uranium thermal assemblies is removed; (b) The 238 U and 208 Pb reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good

  1. Nuclear Measurements, Evaluations and Applications (NEMEA-7) Collaborative International Evaluated Library Organisation (CIELO). Workshop Proceedings

    International Nuclear Information System (INIS)

    Chadwick, Mark; Plompen, Arjan; ); Emmeric Dupont; )

    2014-01-01

    The 7. workshop on Nuclear Measurements, Evaluations and Applications (NEMEA) focused on international collaboration in nuclear data by hosting the kick-off meeting of the pilot project of the Collaborative International Evaluated Library Organisation (CIELO). CIELO aims at fostering nuclear data advances by using the joint expertise of the nuclear data community under the auspices of the OECD Nuclear Energy Agency. The workshop aimed at status reviews of planned and completed contributions and related developments for the CIELO pilot isotopes. The workshop further sought to facilitate in-depth discussions on nuclear data issues which are being addressed in the framework of European Commission projects like ERINDA, EUFRAT, ANDES and CHANDA. The 7. workshop on Nuclear Measurements, Evaluations and Applications (NEMEA) provided an opportunity for the Collaborative International Evaluated Library Organisation (CIELO) to meet and advance its objectives to improve our understanding of neutron reactions on key isotopes that are especially important in nuclear applications, especially in the area of criticality safety and reactors. CIELO is focusing initially on six nuclides ( 1 H, 16 O, 56 Fe, 235 U, 238 U and 239 Pu). These nuclides are important in the aforementioned applications, and despite decades of work many open questions remain to be solved. In some cases, the existing evaluations need improvement because the underlying experimental measurements are either lacking or contradictory. In other cases, nuclear theory work is needed to better advance predictions. In yet other cases, information from cross-section measurements is proving difficult to reconcile with information from integral nuclear criticality experiments or neutron shielding experiments. The main challenges to be faced are as follows: For oxygen, new work is needed to better define the total and elastic cross-sections at lower energies and neutron scattering angular distributions. An outstanding

  2. Evaluation of radionuclide calibrators and scintigraphic cameras used in nuclear medicine in the Sergipe

    International Nuclear Information System (INIS)

    Lima Ferreira, F.C.; Nascimento Souza, D. do

    2008-01-01

    A quality control program to nuclear medicine services concerns the verification of the efficiency of equipment used to diagnosis and treatment, allow the professional improvement. In this study were assessed the performance of two radionuclide calibrators (activimeters) and of two scintigraphic cameras employed in nuclear medicine in the state of Sergipe, Brazil, according to regulation CNEN -NN-3.05. Additionally, to the radionuclide calibrators it was established a nd characterized an intercomparison of activities measured by different practitioners from standard samples of sealed radioactive sources of 133 Ba and 57 Co. The evaluation of this manufacture object was made thought quality control tests on scintigraphic cameras, such as: test of spatial resolution, tomographic resolution and linearity. The results of the quality control tests were satisfactory and they one can be used as parameter in future evaluations. (author)

  3. Advanced gas cooled nuclear reactor materials evaluation and development program

    International Nuclear Information System (INIS)

    1977-01-01

    Results of work performed from January 1, 1977 through March 31, 1977 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Process Heat and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (impure Helium), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes progress to date on alloy selection for VHTR Nuclear Process Heat (NPH) applications and for DCHT applications. The present status on the simulated reactor helium loop design and on designs for the testing and analysis facilities and equipment is discussed

  4. Investigation of knowledge structure of nuclear data evaluation code

    International Nuclear Information System (INIS)

    Uenaka, Junji; Kambayashi, Shaw

    1988-08-01

    In this report, investigation results of knowledge structure in a nuclear data evaluation code are described. This investigation is related to the natural language processing and the knowledge base in the research theme of Human Acts Simulation Program (HASP) begun at the Computing Center of JAERI in 1987. By using a machine translation system, an attempt has been made to extract a deep knowledge from Japanese sentences which are equivalent to a FORTRAN program CASTHY for nuclear data evaluation. With the knowledge extraction method used by the authors, the verification of knowledge is more difficult than that of the prototyping method in an ordinary AI technique. In the early stage of building up a knowledge base system, it seems effective to extract and examine knowledge fragments of limited objects. (author)

  5. Titanium-II: an evaluated nuclear data file

    International Nuclear Information System (INIS)

    Philis, C.; Howerton, R.; Smith, A.B.

    1977-06-01

    A comprehensive evaluated nuclear data file for elemental titanium is outlined including definition of the data base, the evaluation procedures and judgments, and the final evaluated results. The file describes all significant neutron-induced reactions with elemental titanium and the associated photon-production processes to incident neutron energies of 20.0 MeV. In addition, isotopic-reaction files, consistent with the elemental file, are separately defined for those processes which are important to applied considerations of material-damage and neutron-dosimetry. The file is formulated in the ENDF format. This report formally documents the evaluation and, together with the numerical file, is submitted for consideration as a part of the ENDF/B-V evaluated file system. 20 figures, 9 tables

  6. Review of nuclear reaction data evaluation in the US

    Energy Technology Data Exchange (ETDEWEB)

    Howerton, R.J.

    1985-05-01

    The development of the nuclear reaction data evaluation activities in the US over the last 40 years is reviewed, starting with comments on several reports as early as 1944. The review moves on to the development of consortia to share the burden by interchanging sets of data and efforts toward putting together an encoding system and computer-oriented formats. It is predicted that future emphasis is likely to be on charged particle induced reactions. (LEW)

  7. Seismic re-evaluation of French nuclear power plants

    International Nuclear Information System (INIS)

    Andrieu, R.

    1995-01-01

    After a presentation of the seismic inputs which have been taken into account in the design of the French Nuclear Power Plants, the re-assessed values of these inputs are shown. Some considerations about the specificity of the French PWR program with regard to the standardisation of plants are given together with the present objectives of seismic re-evaluations. Finally the main results of the seismic re-analysis being performed for the Phenix Fast Reactor are considered. (author)

  8. Evaluation of nuclear asphalt-content gauges. Final report

    International Nuclear Information System (INIS)

    1989-03-01

    The study evaluated the accuracy and precision of the Troxler, Model 3241-C, and CPN, Model AC-2, Nuclear Asphalt Content Gauges. To achieve precisions at plus or minus 0.15% 95% of the time, it was necessary to establish special procedures for making test samples, controlling environment, and calibration. Both gauges provided acceptable results utilizing a 3-point calibration. Their use in the field would be acceptable when the proper procedures are followed

  9. Review of nuclear reaction data evaluation in the US

    International Nuclear Information System (INIS)

    Howerton, R.J.

    1985-05-01

    The development of the nuclear reaction data evaluation activities in the US over the last 40 years is reviewed, starting with comments on several reports as early as 1944. The review moves on to the development of consortia to share the burden by interchanging sets of data and efforts toward putting together an encoding system and computer-oriented formats. It is predicted that future emphasis is likely to be on charged particle induced reactions

  10. ZZ DOSCROS, Neutron Cross-Section Library for Spectra Unfolding and Integral Parameter Evaluation

    International Nuclear Information System (INIS)

    Zijp, Willem L.; Nolthenius, Henk J.; Rieffe, Henk Ch.

    1987-01-01

    1 - Description of problem or function: Format: SAND-II; Number of groups: 640 fine group cross section values; Nuclides: Li, B, F, Na, Mg, Al, S, Sc, Ti, Cr, Mn, Fe, Co, Ni, Cu, Zn, As, Br, Nb, Mo, Rh, Pd, Ag, In, Sb, I, Cs, La, Eu, Sm, Dy, Lu, Ta, W, Re, Au, Th, U, Np, Pu. Origin: ENDF/B-V mainly, ENDF/B-IV, INDL/V. This library forms in combination with the DAMSIG81 library a convenient source of evaluated energy dependent cross section sets which may be used in the determination of neutron spectra by means of adjustment (or unfolding) procedures or which can be used for the determination of integral parameters (such as damage-to-activation ratio) useful in characterising the neutron spectra. The energy dependent fine group cross section data are presented in a 640 group structure of the SAND-II type. This group structure has 45 energy groups per energy decade below 1 MeV and a group width of 100 KeV above 1 MeV. The total energy span of this group structure is from 10 -10 MeV to 20 MeV. The library has the SAND-II format, which implies that a special part of the library has to contain cover cross section data sets. These cross section data sets are required in the SAND-II program for taking into account the influence of special detector surroundings which may be used during an irradiation. 2 - Method of solution: The selection of the reactions from the evaluated nuclear data libraries was determined by various properties of the reactions for neutron metrology. For this reason all the well- known reactions of the ENDF/B-V dosimetry file are included but these data are supplemented with cross section sets for less well known metrology reactions which may become of interest

  11. Calculation of nuclear reaction parameters with the generator co-ordinate method and their interpretation

    International Nuclear Information System (INIS)

    Beck, R.; Mihailovic, M.V.; Poljsak, M.

    1980-05-01

    Collisions between complex nuclei are described variationally in terms of the GCM with the aim to provide an evidence that it is a manageable calculational procedure. The variational principle of Kohn and Kato is used to derive the expression for the K matrix. The space of scattering states is spanned entirely by antisymmetrized products of shell model wave functions describing separate clusters; the generator coordinate is the separation between the two shell model potentials. Scattering boundary conditions are enforced by solving an integral equation for the channel GC amplitude in each open channel separately. The main part of evaluation of collision parameters is performed by calculating double integrals of a form factor between channel GC amplitudes. A theorem about a property of the form factors is proved which allows reduction of the amount of work needed to calculate double integrals. The application of the method to the elastic 3 H to 4 He scattering has shown the feasibility of the calculation. It is shown how an analysis of calculated scattering parameters and corresponding scattering states in terms of quasibound states enables one to make a consistent comparison with experiment and to extract some knowledge of the reaction mechanism. Finally a comparative list of the calculational procedures of the GCM and RGM for reactions is made. (author)

  12. Study on Economic Evaluation of Nuclear Power Plant's SSC

    International Nuclear Information System (INIS)

    Yun, Eun-Sub; Park, Young-Sheop

    2007-01-01

    As the operating year of nuclear power plant increases, more improvement plans on degraded SSCs(Structure, System, and Component) are suggested. Because of safety concern, the maintenance and replacing cost of nuclear power plant's SSCs are usually high and it can be a burden to financial control. To satisfy both safety and economic problems, systematic and efficient plans are needed. For this reason, KHNP is now developing the LTAM (Long Term Asset Management) program to establish the long term improvement plans for SSCs, from safety and economic point of views. Actually LTAM program is one of the steps of INPO ER (Equipment Reliability) process. In USA, EPRI (Electric Power Research Institute) has developed the LCM (Life Cycle Management) program and it was applied to some nuclear power plants. In this program, several alternatives are candidated. Then, economic evaluation is applied to each alternative. The result of economic evaluation affects to the final alternative decision. In this study, EPRI's economic evaluation method is reviewed

  13. Evaluation Indicators for Analysis of Nuclear Fuel Cycle Sustainability

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Chang Joon; Ko, Won Il; Chang, Hong Lae

    2008-01-15

    In this report, an attempt was made to derive indicators for the evaluation of the sustainability of the nuclear fuel cycle, using the methodologies developed by the INPRO, OECD/NEA and Gen-IV. In deriving the indicators, the three main elements of the sustainability, i.e., economics, environmental impact, and social aspect, as well as the technological aspect of the nuclear fuel cycle, considering the importance of the safety, were selected as the main criteria. An evaluation indicator for each criterion was determined, and the contents and evaluation method of each indicator were proposed. In addition, a questionnaire survey was carried out for the objectivity of the selection of the indicators in which participated some experts of the Korea Energy Technology and Emergency Management Institute (KETEMI) . Although the proposed indicators do not satisfy the characteristics and requirements of general indicators, it is presumed that they can be used in the analysis of the sustainability of the nuclear fuel cycle because those indicators incorporate various expert judgment and public opinions. On the other hand, the weighting factor of each indicator should be complemented in the future, using the AHP method and expert advice/consultations.

  14. Decay data evaluation project: Evaluation of 52Mn and 52mMn nuclear decay data

    Science.gov (United States)

    Luca, Aurelian

    2017-09-01

    All nuclear decay data within the 52Fe-52m,52Mn-52Cr decay chain have been evaluated at IFIN-HH, Romania, as part of an IAEA coordinated research project (F41029) and incorporated into the Decay Data Evaluation Project (DDEP). Both 52Fe and daughter 52Mn are two potentially promising radionuclides to be incorporated into suitable radiopharmaceuticals for PET and SPECT imaging. The decay data evaluation of 52Fe has previously been published and reported to the IAEA Nuclear Data Section. Equivalent DDEP evaluations for 52Mn and 52mMn have also been completed recently, and are presented in summary form below. These improved decay data sets have also been reported to the IAEA in detail, and are highly suitable in dose rate calculations for their application in nuclear medicine.

  15. Relativistic theory of nuclear magnetic resonance parameters in a Gaussian basis representation

    International Nuclear Information System (INIS)

    Kutzelnigg, Werner; Liu Wenjian

    2009-01-01

    The calculation of NMR parameters from relativistic quantum theory in a Gaussian basis expansion requires some care. While in the absence of a magnetic field the expansion in a kinetically balanced basis converges for the wave function in the mean and for the energy with any desired accuracy, this is not necessarily the case for magnetic properties. The results for the magnetizability or the nuclear magnetic shielding are not even correct in the nonrelativistic limit (nrl) if one expands the original Dirac equation in a kinetically balanced Gaussian basis. This defect disappears if one starts from the unitary transformed Dirac equation as suggested by Kutzelnigg [Phys. Rev. A 67, 032109 (2003)]. However, a new difficulty can arise instead if one applies the transformation in the presence of the magnetic field of a point nucleus. If one decomposes certain contributions, the individual terms may diverge, although their sum is regular. A controlled cancellation may become difficult and numerical instabilities can arise. Various ways exist to avoid these singularities and at the same time get the correct nrl. There are essentially three approaches intermediate between the transformed and the untransformed formulation, namely, the bispinor decomposition, the decomposition of the lower component, and the hybrid unitary transformation partially at operator and partially at matrix level. All three possibilities were first considered by Xiao et al. [J. Chem. Phys. 126, 214101 (2007)] in a different context and in a different nomenclature. Their analysis and classification in a more general context are given here for the first time. Use of an extended balanced basis has no advantages and has other drawbacks and is not competitive, while the use of a restricted magnetic balance basis can be justified.

  16. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Massaro, Lawrence M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

  17. INDL/A IAEA Nuclear Data Library for evaluated neutron reaction data of actinides

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1982-05-01

    This Library contains evaluations performed by participants of the IAEA Coordinated Research Project on the Intercomparison of Evaluations of Actinide Neutron Nuclear Data. The data are available on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)

  18. Evaluation of neutron nuclear data for 12C

    International Nuclear Information System (INIS)

    Shibata, Keiichi

    1983-12-01

    Neutron nuclear data of 12 C have been evaluated for JENDL-3 in the energy range from 10 -5 eV to 20 MeV. Evaluated quantities are the total, elastic and inelastic scattering, radiative capture, photon-production, (n,p), (n,d) and (n,α) reaction cross sections and the angular or energy distribution of neutrons and photons. The total cross section below the threshold energy of the inelastic scattering has been calculated on the basis of the R-matrix theory. Three discrete levels have been taken into account for the inelastic scattering. (author)

  19. Statistical evaluation of design-error related nuclear reactor accidents

    International Nuclear Information System (INIS)

    Ott, K.O.; Marchaterre, J.F.

    1981-01-01

    In this paper, general methodology for the statistical evaluation of design-error related accidents is proposed that can be applied to a variety of systems that evolves during the development of large-scale technologies. The evaluation aims at an estimate of the combined ''residual'' frequency of yet unknown types of accidents ''lurking'' in a certain technological system. A special categorization in incidents and accidents is introduced to define the events that should be jointly analyzed. The resulting formalism is applied to the development of U.S. nuclear power reactor technology, considering serious accidents (category 2 events) that involved, in the accident progression, a particular design inadequacy. 9 refs

  20. An evaluation of neutron nuclear data for natural lead

    International Nuclear Information System (INIS)

    Ma Gonggui; Zhou Yiming; Wang Shiming

    1990-04-01

    Complete neutron nuclear data for natural lead were evaluated based on both experimental data measured up to December 1985 and theoretical data calculated with program MUP2. The experimental data evaluation is mainly based on CENDL-1, except (n, 2n) cross section, for which there are newly measured data available. The data, in the neutron energy from 10 -5 eV to 20 MeV, contain cross section, angular distributions and energy spectra of secondary neutrons, and are in ENDF/B-4 format