Analysis of the Source Range Monitor During the First Four Hours of the Three Mile Island Unit 2 Accident

References

• “Analysis of Three Mile Island Unit 2 Accident,” NSAC-80-1, Rev. 1, Nuclear Safety Analysis Center (1980).
   Google Scholar
• K. H. ARDRON and D. G. CAIN, “TMI-2 Accident Core Heat-Up Analysis,” NSAC-24, Nuclear Safety Analysis Center (1981).
   Google Scholar
• H. WARREN, L. BANDA, R. ANDERSON, L. OAKES, W. BENTLEY, A. BUHL, J. JONES and R. MONDAY, “Interpretation of TMI-2 Instrument Data,” NSAC-28, Nuclear Safety Analysis Center (1982).
   Google Scholar
• E. L. TOLMAN, J. H. BROUGHTON, R. K. McCARDELL, S. LANGER, R. R. HOBBINS, W. F. DOMENICO and P. R. DAVIS, “TMI-2 Accident Evaluation Program,” EGG-TMI-7048, EG&G Idaho, Inc. (1986).
   Google Scholar
• E. L. TOLMAN, R. P. SMITH, M. R. MARTIN, R. K. McCARDELL and J. M. BROUGHTON, “TMI-2 Core Bore Acquisition Summary Report,” EGG-TMI-7385, EG&G Idaho, Inc. (1986).
   Google Scholar
• E. L. TOLMAN, J. P. ADAMS, J. L. ANDERSON, P. KUAN, R. K. McCARDELL and J. M. BROUGHTON, “TMI-2 Accident Scenario Update,” EGG-TMI-7489, EG&G Idaho, Inc. (1986).
   Google Scholar
• R. L. CHILDS, D. L. SELBY, J. C. ROBINSON, R. G. CANADA and R. L. MONDAY, “Calculation of the TMI-2 Source-Range Monitor Reading for Several Core Water Levels,” Trans. Am. Nucl. Soc., 34, 558 (1980).
   Google Scholar
• P. S. PICKARD, J. S. PHILBIN, W. E. NELSON and E. STRAKER, “Neutronic Sensitivity Analysis of the SRM Response for the TMI-2 Accident,” Trans. Am. Nucl. Soc., 34, 559 (1980).
   Google Scholar
• D. J. MALLOY and Y. I. CHANG, “Neutronic Analysis of the Three Mile Island Unit-2 Ex-Core Detector Response,” ANL-81-75, Argonne National Laboratory (1981).
   Google Scholar
• GPU Nuclear TMI-2 Division, “Quick Look Inspection Results,” Data Report TPO/TMI-26, GPU Nuclear Corporation (1982).
   Google Scholar
• GPU Nuclear TMI-2 Division, “Fuel Conditions and Locations,” TMI-2 TPO/TMI-166, Technical Planning Department, GPU Nuclear Corporation (1985).
   Google Scholar
• “Quick Look Inspection: Results,” Vol. II, GEND-030, Bechtel Northern Corporation (1983).
   Google Scholar
• M. W. CRUMP and J. C. LEE, “Calculation of Spatial Weighting Function for Ex-Core Neutron Detectors,” Nucl. Technol., 41, 87 (1978).
   Web of Science ®Google Scholar
• E. W. OKYERE, “A Non-Invasive Liquid Level/Density Measurement in Pressure Vessels,” PhD Thesis, The Pennsylvania State University, Department of Nuclear Engineering (1985).
   Google Scholar
• B. R. BANDINI, A. J. BARATTA and V. R. FRICKE, “Determination of the End State of the Three Mile Island Unit 2 Accident Using Neutron Transport Analysis, Nucl. Technol., 81, 370 (1988).
   Web of Science ®Google Scholar
• W. A. RHOADES and R. L. CHILDS, “DOT 4.3, One- and Two-Dimensional Transport Code System,” CCC-429, Radiation Shielding Information Center (1982).
   Google Scholar
• “Loft System and Test Description (5.5 Ft Nuclear Core LOCEs),” NUREG/CR-0169, EGG-2231, U.S. Nuclear Regulatory Commission (Apr. 1983).
   Google Scholar
• S. NAKAMURA, “Point Reactor Kinetics (PRK) Code,” Ohio State University, Department of Nuclear Engineering (1977).
   Google Scholar
• M. J. BELL, “ORIGEN-The ORNL Isotope Generation and Depletion Code,” CCC-217, Oak Ridge National Laboratory (1977).
   Google Scholar
• R. GOLD, J. H. ROBERTS, F. H. RUDDY, C. C. PRESTON and W. N. McELROY, “Solid State Track Recorder Neutron Dosimetry in the Three Mile Island Unit-2 Reactor Cavity,” HEDL-7484, Hanford Engineering Development Laboratory (1984).
   Google Scholar
• R. W. ROUSSIN, “VITAMIN-E: A Coupled 174-Neutron, 38-Gamma Ray Multigroup Cross Section Library for Deriving Application-Dependent Working Libraries for Radiation Transport Calculations,” DLC-113, Radiation Shielding Information Center (1984).
   Google Scholar
• N. M. GREENE, J. L. LUCIUS, L. M. PETRIE, W. E. FORD III, J. E. WHITE and R. Q. WRIGHT, “AMPX-II, A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B,” ORNL/TM-3706, Oak Ridge National Laboratory (1978).
   Google Scholar
• W. W. ENGLE, Jr., “A User’s Manual for ANISN-A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering,” CCC-254, Radiation Shielding Information Center (1973).
   Google Scholar
• “Radiation Shielding Benchmark Problems,” ORNL-RSIC-25 (ANS-SD-9), Oak Ridge National Laboratory (1979).
   Google Scholar
• C. M. ALLISON, S. T. POLKINGHORNE and M. S. SOHAL, “SCDAP/MOD1 Analysis of the Progression of Core Damage During the TMI-2 Accident,” EGG-SAR-7104, EG&G Idaho, Inc. (1985).
   Google Scholar
• J. R. WORSHAM, “Methods and Procedures of Analysis for TMI-2 Criticality Calculation to Support Recovery Activities Through Head Removal,” Technical Report BAW-1738, Babcock & Wilcox (June 1982).
   Google Scholar