- NUREG/CR|0200 ORNL/NUREG/CSD|2/R4|^/ / Vol. 1🔍
- 2000/05/31|NUREG/CR|0200 Vol 2 Part 1 Rev 6 "SCALE Ver 4.4🔍
- SCALE|4 Analysis of Pressurized Water Reactor Critical ...🔍
- 2000/06/30|NUREG/CR|0200 Vol 1 Part 1 Rev 6 "SCALE Ver 4.4🔍
- Validation of the ORIGEN|S code for predicting radionuclide ...🔍
- NUREG/CR|6613🔍
- NUREG/CR|5500🔍
- NRC|RADTRAN Technical Documents🔍
NUREG/CR|0200 ORNL/NUREG/CSD|2/R4|^/ / Vol. 1
NUREG/CR-0200 ORNL/NUREG/CSD-2/R4-^/ / Vol. 1, Rev. 4
Also available are regulatory guides, NRC regula- tions in the Code of Federal Regulations, and Nuclear Regulatory Commission Issuances.
2000/05/31-NUREG/CR-0200 Vol 2 Part 1 Rev 6 "SCALE Ver 4.4
... 1. Oak Ridge National Laboratory. Prepared for. U.S. Nuclear Regulatory Commission. Page 2. NUREG/CR-0200, Rev. 6. ORNL/NUREG/CSD-2/1R6. Vol. 2, Part 1. SCALE: ...
SCALE-4 Analysis of Pressurized Water Reactor Critical ... - INFO
S2 of SCALE: A Modular Code System for Performing. Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Rev. 4. (ORNL/NUREG/CSD-2/R4), Vols.
2000/06/30-NUREG/CR-0200 Vol 1 Part 1 Rev 6 "SCALE Ver 4.4
Page 1. NUREG/CR-0200, Rev. 6. ORNLUNUREG/CSD-2/R6. Vol. 1, Part 1. SCALE. Version 4.4. A Modular Code System for Performing. Standardized Computer Analyses for ...
Validation of the ORIGEN-S code for predicting radionuclide ...
[1]. J.C. Tait, I.C. Gauld, G.B. Wilkin. Derivation of Initial Radionuclide ... NUREG/CR-0200, Revision 4 ORNL/NUREG/CSD 2/R4, vols. I, 11, and III (1990).
SCALE: A Modular Code System for Performing Standardized ...
Page 1. NUREG/CR-0200. ORNL/NUREG/CSD-2/R4-VoJ3. Vol. 3, Rev. 4. SCALE: A Modular Code System for Performing Standardized. Computer Analyses for. Licensing ...
NUREG/CR-6613, Vol. 2, "Code Manual for MACCS2 Preprocessor ...
The primary pathways by which people may be exposed to ionizing radiation emitted by radionuclides released during a nuclear accident are: 1. external exposure ...
NUREG/CR-5500, Vol. 2 INEEL/EXT-97-00740 - NRC
Unavailability Estimates Based on Component Operational Data.... 3.2.1 Fault Tree Unavailability Results. 3.2.2 Fault Tree Uncertainty Analysis.. 3.3.
Figures 1 and 2). There are, however, still some problems. One problem is readily ... Between 2 and 14000 Seconds. NUREG/CR-0171, ORNL/NUREG-47, Oak Ridge.
NRC-RADTRAN Technical Documents - RAMP Website
Description. NUREG-0170, Volume 1, “Final Environmental Statement on the ... Description. NUREG-0170, Volume 2, “Final Environmental Statement on the ...
Data Testing of ORNL 235U Evaluation; R.Q. Wright, L.C. Leal and ...
Evaluation, NUREG/CR-0200, Rev. 4 (ORNL/NUREG/CSD-2/R4), Vols. I, II, and III. (April 1995). Available from Radiation Shielding Center as CCC-545. ་་་. Page 6 ...
NUREG/CR-5591 ORNL/TM-11568 Vol. 2, No. 2
The primary objective of the HSSI Program Tenth. Irradiation Series is to investigate the postirradiation fracture toughness of the SAW from the Midland. Unit 1 ...
This report was prepared to provide support for major revisions to the current U.S. Nuclear Regulatory Commission decay heat rate guide entitled "Regulatory ...
Update of the Nuclear Criticality Slide Rule for the Emergency ...
B. L. Broadhead et al., “An Updated Nuclear Criticality Slide Rule: Technical Basis,” Report NUREG/CR-6504 Vol. 1 ORNL/TM-13322/V1, (1997). ... 2 ORNL/TM-13322/V2 ...
Expanded Materials Degradation Assessment (EMDA) Volume 3
... NUREG/CR-7153, Vol. 3. ORNL/TM-2013/532. Page 2. NRC Reference Material. As of November 1999, you may electronically access. NUREG-series publications and other ...
An Updated Nuclear Criticality Slide Rule
Page 1. NUREG/CR-6504, Vol. 2. ORNL/TM-13322/V2. An Updated Nuclear Criticality. Slide Rule. Functional Slide Rule. Prepared by. C. M. Hopper, B. L. Broadhead.
NUREG CR-7289, "Nuclear Data Assessment for Advanced Reactors"
advanced reactor specifications, (2) analysis of previous studies performed at ORNL and other ... 1 data, is illustrated in Figure 1-2. The diagonal elements ...
VALIDATION OF SCALE-4 CRITICALITY SEQUENCES ... - OSTI.GOV
1. SCALE: A Modular Code System for Performing Stan- dardized Computer Analyses for Licensing Evaluation,. NUREG/CR-0200, Rev. 4 (ORNL/NUREG/CSD-2/R4),. Vols.
Bounding Criticality Safety Analyses for Shipments of Unconfigured ...
Evaluations, NUREG/CR-0200, Rev. 4 (ORNL/NUREG/CSD-2/R4), Vols. I-III (April. 1995). Available from Radiation Safety Information Computational Center, Oak ...
Latest Results of the United States Nuclear Regulatory Commission ...
NUREG/CR-4183 (ORNL/TM-9567), Oak Ridge National Laboratory, Oak Ridge, TN ... NUREG/CR-6471, Vol. 2, U.S. Nuclear Regulatory Commission, Washington ...