67 results on '"group constants"'
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2. Fine structure effects and the central worth discrepancy
3. Integrated system for production of neutronics and photonics calculational constants. Volume 5, revision 1. CLYDE, a code for the production of calculational constants from nuclear data. [For CDC-7600 computer]
4. Standard thermal energy group structure for generation of thermal group constants from ENDF/B data
5. XSMOD: a code for the modification of the Los Alamos Master Data File
6. Rapid calculational method for multigroup elastic transfer
7. Fine group calculations for reactivity coefficients of structural materials in fast reactors
8. Assessment of neutron group constants for iron and stainless steel through measurements and analyses of energy and space distributions of neutrons in test assemblies
9. Shielding factor interpolation schemes
10. Recent trends towards the dose hazard: reference standards for different radionuclide groupings
11. Calculation of the reactivity pattern of the KWO reactor during the first cycle
12. Introduction to nuclear reactor and nuclear power plant techniques. I. Foundations, reactor physics, reactor dynamics; Einfuehrung in die Kernreaktor- und Kernkraftwerkstechnik. T. 1. Kernphysikalische Grundlagen, Reaktorphysik, Reaktordynamik
13. Moderation and absorption of resonance neutrons; Zamedlenie i pogloshchenie rezonansnykh neitronov
14. Assessment of fast-reactor group constants for some reactor materials through measurements and analyses of energy- and space-distributions of fast neutrons in test assemblies
15. Analysis of integral experiments performed on fast critical assemblies
16. Comparison of large fast reactor physics characteristics calculated by various methods and constants
17. Effect of higher plutonium isotopes and new delayed neutron data on fast reactor dynamic calculations
18. Critical size and central reaction rate results from the MOZART programme and their predictions
19. U.S. theoretical and computational program
20. Analysis of FCA critical experiments and its application to JOYO nuclear design
21. Intercomparison of large fast power reactor calculations
22. Nuclear data and integral measurement correlation for fast reactors
23. Three-dimensional burn-up calculation in fast reactors
24. Three-dimensional burn-up calculation in fast reactors
25. Effect of elastic scattering removal cross section on neutron spectra
26. Study on the error of lumped cross section set of fission products
27. Revision of JAERI-FAST Set based on bench mark test
28. Measurements and analysis of the Doppler effect of structural materials
29. Analysis of heterogeneous effect of plate cell
30. Proceedings of the international symposium on physics of fast reactors, Tokyo, Japan, October 16--19, 1973. Volume II
31. Neutron thermalization and data preparation for light-water reactors
32. Methods to account for fine-structure effects in multigroup reactivity calculations
33. Multiregion equivalence relation for resonance heterogeneity effects
34. Effective admixture cross section in plate lattice heterogeneous systems
35. Rapid calculational method for multigroup elastic transfer
36. Theory of resonance-group self-shielding
37. Influence of deep minima on multigroup cross-section generation
38. Recent advances and outstanding topics in fast reactor physics
39. Comments on the comparison of energy multigroup transport and diffusion theory solutions of the fast neutron penetration problem
40. Analysis of dieaway experiments in a uranium-238 sphere
41. A comparison of data libraries for thermal fuel cell calculations
42. Comparison of group constants using single- and multi-level formulas for the resolved resonance region of uranium-235 and uranium-233
43. Improvements in transport theory and their applications to fast neutron spectra
44. Interpretation of the central cell reactivity worth and experimental determination of a characteristic value of the reactor cell composition K/sub m/$sup +$
45. Conditions of fast multiplying systems for existence of the time eigenvalue of the fundamental mode
46. Modification to fissile element cross sections and their influence on the calculated parameters of fast critical assemblies
47. Cross-section standardization for thermal power reactors. Final report
48. Development of ENDF/B-IV multigroup neutron cross-section libraries for the LEOPARD and LASER codes. Technical report on Phase 1
49. A basic study on the adjustment of group cross sections by means of integral data
50. Two-dimensional multigroup diffusion burnup code APOLLO for fast reactor long-term burnup analysis
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