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32 results on '"Yasunobu Nagaya"'

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1. Estimation of Continuous Distribution of Iterated Fission Probability Using an Artificial Neural Network with Monte Carlo-Based Training Data

3. Japanese evaluated nuclear data library version 5: JENDL-5

4. Development of JAEA Advanced Multi-Physics Analysis Platform for Nuclear Systems

5. General-purpose Nuclear Data Library JENDL-5 and to the Next

6. 新しい核データ処理システムFRENDYの開発と検証

7. Development of a Nuclear Data Processing Code FRENDY Version 1

8. Calculation of reactor kinetics parameters with Monte Carlo differential operator sampling

9. Azimuthal flux distribution measurements around fuel rods in reduced-moderation LWR lattices

10. Void reactivity evaluation by modified conversion ratio measurements in LWR critical experiments

11. Intra-pellet neutron flux distribution measurements in LWR critical lattices

13. JENDL-4.0 Integral Testing for Fission Systems

14. On Effective Delayed Neutron Fraction Calculations with Iterated Fission Probability

15. Calculation of effective delayed neutron fraction with Monte Carlo perturbation techniques

16. JENDL-4.0 Benchmarking for Fission Reactor Applications

17. Comparison of Monte Carlo calculation methods for effective delayed neutron fraction

18. Evaluation and use of the prompt fission neutron spectrum and spectra covariance matrices in criticality and shielding

19. Impact of Incident Energy Dependence of Prompt Fission Neutron Spectra on Uncertainty Analyses

20. Comparison of Resonance Elastic Scattering Models Newly Implemented in MVP Continuous-Energy Monte Carlo Code

21. Evaluation of sensitivity coefficients of effective multiplication factor with respect to prompt fission neutron spectrum

23. Impact of Perturbed Fission Source on the Effective Multiplication Factor in Monte Carlo Perturbation Calculations

24. Cold neutron production in solid and liquid moderators. II: on the reentrant-hole configuration

25. Neutronic study of spherical cold-neutron sources composed of liquid hydrogen and liquid deuterium

26. 3D radiation transport benchmark problems and results for simple geometries with void region

27. Reference solutions for 3-D radiation transport benchmarks by a Monte Carlo code GMVP

28. FRENDY: A new nuclear data processing system being developed at JAEA.

30. Calculation of Reactor Kinetics Parameters βeff and Λ with Monte Carlo Differential Operator Sampling

31. Recent Developments of JAEA’s Monte Carlo Code MVP for Reactor Physics Applications

32. An analysis of a heterogeneous core using Green's function

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