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2. Resource Letter FuNP-1: The Future of Nuclear Power

Catalog

Books, media, physical & digital resources

3. A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent-Fuel Pool Storage

4. ORIGEN-ARP, A Fast and Easy-to-Use Source Term Generation Tool

5. Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries

6. Evaluation of Shielding Analysis Methods in Spent-Fuel Cask Environments

7. Validation of SCALE-4 for Burnup Credit Applications

8. [Untitled]

9. Plutonium Production Using Natural Uranium From the Front-End of the Nuclear Fuel Cycle

10. Review of Technical Issues Related to Predicting Isotopic Compositions and Source Terms for High-Burnup LWR Fuel

11. A Critical Review of Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage

12. Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel

13. EMSP project summary (Project ID: 60077): Development of nuclear analysis capabilities for DOE waste management activities

14. Assessment and recommendations for fissile-material packaging exemptions and general licenses within 10 CFR Part 71

15. Development of nuclear analysis capabilities for DOE waste management activities. 1998 annual progress report

16. Development of nuclear analysis capabilities for DOE waste management activities

17. ARP: Automatic rapid processing for the generation of problem dependent SAS2H/ORIGEN-s cross section libraries

18. Dose consequences from a postulated criticality occurring in a low-level waste disposal facility

19. Recommendations for preparing the criticality safety evaluation of transportation packages

20. Statistical analysis of radiochemical measurements of TRU radionuclides in REDC waste

21. OECD/NEA burnup credit calculational criticality benchmark Phase I-B results

22. Shielding and criticality analyses of phase I reference truck and rail cask designs for spent nuclear fuel

23. Adequacy of the 123-group cross-section library for criticality analyses of water-moderated uranium systems

24. Investigation of nuclide importance to functional requirements related to transport and long-term storage of LWR spent fuel

25. Validation of the scale system for PWR spent fuel isotopic composition analyses

27. Application of Differential Sensitivity Theory to a Neutronic/Thermal-Hydraulic Reactor Safety Code

28. Criticality Analysis Support for the Three Mile Island Unit 2 Fuel Removal Operations

29. Authors

30. Assessment of shielding analysis methods, codes, and data for spent fuel transport/storage applications. [Radiation dose rates from shielded spent fuels and high-level radioactive waste]

31. Thermal-hydraulic differential sensitivity theory. [LMFBR]

32. Parametric study of radiation dose rates from rail and truck spent fuel transport casks

33. Multicode comparison of selected source-term computer codes

34. ADJOINT SENSITIVITY ANALYSIS OF EXTREMUM-TYPE RESPONSES IN REACTOR SAFETY

35. Eigenvalue sensitivity theory for resonance-shielded cross sections

36. Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques