UNI/ll!!!WIHUI!!!”(WIN)”!!! "WWW/WIN” 01—: (9—: _cnoo1 '—I I LIBRARY Michigan Sta” University This is to certify that the thesis entitled A NEUTRON ACTIVATION ANALYSIS PROCEDURE DEVELOPED FOR USE AT THE MICHIGAN STATE UNIVERSITY NUCLEAR REACTOR LABORATORY presented by STEVEN" A. LE LEWER has been accepted towards fulfillment of the requirements for M.S. degree in Chemical Engineering g9“ (g2. ng'eél’ , Major professor Date May 16, 1978 0-7639 fl--\\\\ L ll‘ to "I \ air “an”, . JCT,” 1-199: .' E 93:9,, OVERDUE FINES: 25¢ per day per item RETURNING LIBRARY MATERIALS . Place in book return toreno charge from circulation records A NEUTRON ACTIVATION ANALYSIS PROCEDURE DEVELOPED FOR USE AT THE MICHIGAN STATE UNIVERSITY NUCLEAR REACTOR LABORATORY BY Steven Arthur Lelewer A THESIS Submitted to Michigan State University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Department of Chemical Engineering 1978 ABSTRACT A NEUTRON ACTIVATION ANALYSIS PROCEDURE DEVELOPED FOR USE AT THE MICHIGAN STATE UNIVERSITY NUCLEAR REACTOR LABORATORY BY Steven Arthur Lelewer The purpose of this thesis is to describe the development of a method of performing neutron activation analysis at the Michigan State University Nuclear Reactor Laboratory. One requirement of the method was that it could be performed in a reasonable amount of time. Manual spectrum analysis is a long and tedious procedure. Philip A. Baedecker developed a spectral analysis computer program entitled SPECTRA. Part of the project described in this thesis entailed modifying SPECTRA to operate on the Michigan State University CDC 6500 computer. SPECTRA requires that the spectrum data be input via punched cards. An interface was designed to allow the interconnection of the Nuclear Data multichannel analyzer and the engineering building IBM 1800 computer. Program ND was created to control the transfer of data from the analyzer to the IBM 1800, and to handle the formatting and punching of the data onto cards for input to program SPECTRA. A 2048 Steven Arthur Lelewer channel spectrum can be transferred from the Nuclear Data analyzer to the IBM 1800 in approximately 15 seconds. The spectral analysis can be performed by SPECTRA at a cost of $1 to $2 on the campus computer. The final chapter of the thesis provides a detailed procedure for transferring the data from the Nuclear Data analyzer to the IBM 1800, including cable hook-ups and the oepration of the IBM 1800 computer. The procedure also incudes instructions for the usage of program SPECTRA. ACKNOWLEDGEMENTS The author would like to thank Professors Bruce Wilkinson and George Coulman for their guidance, time and friendship. Thanks should be given to Les Keith of the Engineer- ing Building Computer Laboratory for his assistance in the development of the interface circuitry and to Robert Morris of Norwalk, California, a computer science student, for his assistance in the modifications of program SPECTRA. A special thanks goes to my wife, Debby, for her moral support, understanding, and encouragement. ii TABLE OF CONTENTS Page LIST OF FIGUES C O C O O O O O O O O O O O O O O O 0 iv INTRODUCTION 0 C O O O O O O O O 0 C O O O O O O O O O 1 THE INTERFACE AND THE ND PROGRAM. . . . . . . . . . . 7 SPECTM . O C O O O O O O O O O O O O O O O O O O O O 15 USER ' S WUAL O O O O O O O I C C C C O O O O O O O O 2 3 BIBLIOGRAPHY. . . . . . . . . . . . . . . . . . . . . 33 APPENDIX A: A Listing of Program ND. . . . . . . . . 35 APPENDIX B: A Listing of Program Spectra . . . . . . 48 APPENDIX C: A Description and Listing of the Program Spectra by Philip A. Baedecker. . . . . . . . . . . . . . . . 70 iii LIST OF FIGURES Figure Page 1 Wiring Schematic for Interface. . . . . . . . . 10 2 Typical Photopeak and Compton Edge. . . . . . . 19 3 ND Analyzer--Interface--IBM 1800 Cable HOOk'UpS o o o o o o o o o o o o o o e e o e o 24 iv INTRODUCTION Neutron activation analysis (NAA) is a powerful laboratory technique for determining the elemental content of an unknown sample. NAA is a particularly valuable tool in that it is often possible to identify trace amounts of elements in quantities of parts per million or even parts per billion. When the unknown sample is neutron irradi- ated, radioactive isotopes are formed. Many of the isotopes thus formed decay by gamma emission. Examination of the energy spectrum of the gamma rays emitted will identify the elements contained in the unknown sample. A multichannel analyzer coupled with a gamma ray radiation detector is used to collect the spectral data of the irradiated sample. Elemental identification is performed by analysis of the energies of the photopeaks observed in the collected spectrum. Analysis of the photopeak height, sample irradiation time, counting time, time between irradiation and data collection, sample weights or volumes, and detector efficiency will allow the determination of the quantity of each element present in the unknown sample. Another feature of NAA is its insensitivity to chemical form of the irradiated sample. In order to more fully understand NAA, a few basic concepts will be discussed. An atomic nucleus is only stable when a specific number of protons and neutrons are present. The number of protons in the nucleus determines the element's identity and the number of neutrons usually determines whether that nucleus is radioactive or non- radioactive (stable). (It should be noted that there are some elements that have no stable nuclei. In some cases, there are other differences that make nuclei radioactive.) As a sample case, all sodium atoms contain 11 protons, while only those sodium atoms containing 12 neutrons are stable. A sodium atom with fewer or with more neutrons will be radioactive. There are elements that have more than one number of neutrons that result in stability; for instance, tin has ten stable isotopes. Nuclei can absorb additional neutrons, resulting in the conversion of stable nuclei to radioactive ones. The radioactive nuclei decay in unique ways and emit radiations that are often distinct and can be measured even in very small quantities. The measurement of the radiations can determine the kind and the number of radio— active atoms that are present. The neutron bombardment of a sample is performed in a nuclear reactor where the neutrons that strike the target atoms have been slowed down so that they have very little energy of motion. These free neutrons react with the target nuclei resulting in the capture of the neutron and thus creating nuclei with atomic weights one unit greater than the original atomic weight. These newly- created nuclei are typically radioactive. Radioactive nuclei almost always decay by emitting negatively charged beta particles, usually accompanied by gamma rays. Each kind of radioactive atom decays with a unique pattern called a decay scheme. By measuring the radiation and identifying the pattern, the source of radi- ation can be determined. There are some problems in the measurement of gamma rays. These problems are due to the interaction of gamma rays with matter. Due to these inter- actions, the gamma rays measured by the detector no longer have the energy they started with at the time of emission. The most troublesome of the interactions is Compton scattering. The Compton effect is a collision between a gamma ray and an electron. Compton scattering will generally involve the outer atomic electrons. When the gamma ray collides with the electron, it only transfers part of its energy. The gamma ray is degraded in energy and deflected from its original path. Compton scattering is the prevail- ing interference for measurement of gamma rays with energies greater than .5 MeV. Assuming that the radioactive isotope being detected has a 1 MeV gamma ray emission, due to the Compton effect, the detector will see gamma rays at 1 MeV and a smear of gamma rays from 0 Rev to a value which is approximately 250 Rev less than the original gamma ray energy (for this case, 750 KeV). The end of the smear at 250 Kev less than the original gamma ray energy is called the Compton edge. This smear of gamma rays raises the background counts in the lower-energy gamma ray region. Therefore if low-energy gamma rays are being emitted from another radioactive isotope, the Compton effect from the 1 MeV gamma rays may mask them and make identification of the low-energy emitting isotope difficult. Interaction of gamma rays with matter may effect the sensitivity of the analysis, but the use of good gamma ray detectors can minimize the interference effects. The applications for activation analysis seem unlimited. The only requirement for its use is that the element of interest must yield a gamma ray emitting isotope after irradiation. NAA has been used in the electronics industry to determine trace levels of impurities in semi- conductors and the dopant levels in finished semiconductors. It has been useful in detecting trace amounts of oxygen in steel. NAA can be used to detect traces of catalyst residues in plastics. Determination of residual amounts of bromide in foodstuffs and on crops has assisted the agricultural industry. NAA has provided a new tool for the forensic chemist. The results of activation analysis have been admitted as evidence in a court of law. NAA can be used to trace a sample of paint, grease, tire rubber, etc. to its manufacturer by the quantities of trace elements present. It can provide a reliable method of identifying traces of gunpowder on a suspect's skin. Another attractive use of NAA is the introduction of minor quantities of several easily activated elements as a secret coding to guard against counterfeiting of a product. This method of product identification is being considered for use in drugs, foodstuffs, cement and legal tender. The tOpic of this paper will be the development and usage of a computerized method of neutron activation analysis utilizing the Michigan State University Triga Mark I nuclear reactor, a Nuclear Data multichannel analyzer, an IBM 1800 computer and the Michigan State University CDC 6500 computer. Prior to the development of this procedure, NAA was performed by manual techniques. A complex spectrum could take many hours to complete. Utilizing the methods described in this paper, spectrum analysis can be completed in a few minutes with a computer usage cost of a few dollars. Included in this paper will be a discussion of the electronic interface developed to allow data transfer from the Nuclear Data multichannel analyzer to the IBM 1800 computer, a discussion of the computer program developed to control the data transfer and to present the data on computer punch cards, and a discussion of the spectral analysis computer program developed for the CDC 6500 computer. The final tOpic of this paper will be a user's manual giving instructions on performing NAA utilizing the facilities available at Michigan State University. THE INTERFACE AND THE ND PROGRAM Prior to the design of the interface and the development of the ND program, there were only two forms of data output for the Nuclear Data analyzer. The first, a pen plotter, provided rapid data output. Its disadvan- tage was that when peak height analysis was performed by calculating the area beneath the peak, the result was quite inaccurate. The second form of output available was through- a Teletype with a paper tape punch. The Teletype output allowed peak height analysis with a high degree of accur- acy, but to output a 2048 channel spectrum required approx- imately 30 minutes. Therefore, the first step necessary for a project that involved experiments using the Nuclear Data multichannel analyzer to count many samples was to find a method of data output that was both rapid and accurate. A bid request for an interface to connect the Nuclear Data analyzer to the IBM 1800 computer was sent to IBM and to Nuclear Data. The cost reported was in excess of the budget for the project. It was decided at this point that the interface design was to be performed in-house. To develop the interface, the following informa- tion had to be ascertained: (a) location of an output port on the Nuclear Data analyzer where memory bank data was available in some binary format; (b) the binary format of the data at the output port (i.e.: is the data in pure binary (base 2) or in 1—2-4-8 binary coded decimal, where any four bits (on-off switches) represents one decimal digit. In four bits, "0" through "9" can be represented); (c) voltages at the output port which represented O and l; (d) location of an input port on the Nuclear Data analyzer where the memory bank data at the output port could be advanced; (e) voltage needed at the input port to trigger the data to advance as described in (d); (f) location of an input port on the IBM 1800 where the data could be received; (9) the voltages required at the input port to represent 0 and 1; (h) the location of an output port on the IBM 1800 where an advance signal could be generated to trigger the data advance; (i) voltages generated at the output port for 0 and l representation. Many hours were spent researching the operation and main- tenance manuals for both the Nuclear Data analyzer and the IBM 1800. This research, coupled with extensive experi- mentation, yielded the necessary information. It was found that at the connector labeled "Printer A" on the Nuclear Data analyzer, the memory bank data could be read in l-2-4-8 binary coded decimal form with voltages pulled down to within 0.5 volts of ground for "zero" signals and up to +6 volts or floating for "one" signals. It was also discovered that the memory bank could be advanced by simulating a "complete" signal of +12 volts. This was the voltage that the plotter generated to indicate that data had been received and that the next channel of data should be prepared for transfer. The digital inputs or "DI's" on the IBM 1800 were determined to be the best port for data input and the digital outputs (called "DO's" or "ECO's") were found to be the source for genera- tion of the trigger signal. It was determined that for the IBM 1800, a zero was represented by -12 volts (with a range of -6 to -30 volts), and a one by 0 volts (with a range of -l to +30 volts). An electronic interface was required to adjust the voltages to conform with the needs of the two devices being connected. The Michigan State University Department of Engineering Research Computer Laboratory developed an interface box powered by the Nuclear Data analyzer NIM bin that provided the required voltage conversions (see Figure 1). It is important to note here that the voltage 10 .oommuoucH MOM oaquonom mcflufi3||.H wusmfim >N_ + C 0mm 00m OOQ - r 33.38 oz vocz N 5 OOQ EOZMZ OZ >N_.. ll conversions performed by the interface only shift the voltages; they are not reversed. Therefore a "1" generated by the ND analyzer, with voltage shifted by the interface, yields a "0" at the IBM 1800, and a "0" generated by the ND analyzer, with voltage shifted by the interface, yields a "1" at the IBM 1800. The correcting inversion is per- formed by program ND as the data is transferred. Once the hardware was developed to enable the IBM 1800 and the Nuclear Data analyzer to communicate with each other, it was necessary to create a program to con- trol the transfer of data from one device to the other. Program ND was written to perform this function. (A listing of ND is provided in Appendix A). Program ND is an interactive program written in Fortran IV. The program elicits information from the user, such as the number of data channels to be transferred and whether or not a line printer listing of the spectrum is desired. The program also instructs the user, with commands to load the card hopper when necessary and to make sure the ND analyzer is properly prepared for data transfer. Program ND consists of seven parts. The first of these parts is the main program. The main program con- trols the operation of the rest of the code. The responses of the user to the questions asked by the computer control the title of the experiment, the run number and the form 12 of output. The main program calls upon the six subprograms listed below: (1) Subroutine PRINT is called when the user requests a listing of the data transferred. This listing is outputted to the line printer. Subroutine PRINT con- verts the binary data to the equivalent character code and fills in leading blanks instead of zeros as needed (when the ND analyzer sends the data in a channel, six digits are transmitted. A count of 900 is sent as 000900). The program also prints the number of the first channel in each row of data listed. (2) Subroutine PPUNC is called when the user requests a deck of cards containing the data transferred. The deck is punched in binary coded decimal form. A BCD deck contains ten channels of data on each card. Each column on the card contains either a blank or one numeri— cal character. Subroutine PPUNC performs the same con- version from binary that subroutine PRINT performs, but no "first channel" is punched on the cards. (3) Function MINO is called by the main program to calculate which of two numbers is the minimum. (Note: The following three subroutines are written in IBM 1800 Assembly language. Because of the necessity to do bit manipulation, the use of Assembly language is more practical and efficient than the use of Fortran.) l3 (4) Subroutine DI is called by the main program to read the digital inputs from the ND analyzer and to send the "complete" signal to the ND analyzer to advance the memory stack. Subroutine DI also performs the conver— sion of the input bits from 0 to l and l to 0. This routine also loads the 1-2-4-8 BCD data into a special portion of the IBM 1800 computer memory called "COMMON," converts the 1-2-4-8 BCD data digits to binary and loads the binary data into "COMMON“ also. (5) Subroutine ECO is called by the main program to ensure that the digital output port is initialized prior to the ND analyzer being turned to the "Read in/out" mode. This is required so that the first channel of data is not missed. (6) Subroutine CRUNC is called by the main program when the user requests a "crunch" deck. A crunch deck contains 40 channels per card. The data is in binary form. Each column on the card contains 12 bits of information. Since each word or channel of data requires a maximum of 16 bits when converted to binary, each word requires 1% columns. In other words, every four columns contains three data channels. This format is similar to the "crunch" format used in the MSU Cyclotron Laboratory. The CDC 6500 remote input station located in the engineer- ing building is not capable of transmitting binary data to the computer. The spectrum analysis routine, SPECTRA, 14 available on the CDC 6500 is not provided with the ability to handle the "crunch" decks. The "crunch" feature is provided here in Program ND, but further development of Spectra would be necessary in order to make use of this feature. SPECTRA Program SPECTRA is used to analyze the data decks generated by the IBM 1800 and program ND. Spectra was originally created by Philip A. Baedecker. A description and listing of the program is provided in Appendix C. Spectra was then brought to the Michigan State University Cyclotron Laboratory and modified to operate on the Sigma 7 computer. This conversion was performed by Dr. Charles Spooner of the Geology department along with members of the cyclotron staff. The original Spectra was designed to accept tape input of the spectrum. The cyclo- tron version of Spectra utilized a compressed binary format ("crunch") deck of data cards for input. To allow use of Spectra with the data generated by the IBM 1800 computer and program ND, the computer code was modified with the assistance of Robert Morris, a computer science student at MSU. As a result of this modification, campus-wide use of Spectra through the CDC 6500 computer became possible. The CDC 6500 version of Spectra is designed to accept BCD decks of input data as provided by the IBM 1800 and program ND. A listing of the CDC 6500 version of Spectra is provided in Appendix B. 15 16 Spectra is a computer program that analyzes gamma ray spectrum by searching out photopeaks, calculating the area under the peaks, finding the centroid of each peak and providing the energy corresponding to each peak. In activation analysis runs, when quantitative information is required, the program provides either the concentra- tions or the quantity of the elements in the unknown samples. Control of the program is accomplished when the user places certain control cards in front of the data decks to be analyzed. A detailed set of instructions for use of Spectra can be found in Chapter 4, the User's Manual- The following procedure outlines the method by which the program analyzes the data. After reading in the control cards, the program reads in a data deck. The data can be smoothed by a five-point convolution method. Since smoothing can cause undershoot of the baseline on either side of very narrow peaks, smoothing should be avoided for Spectrum with 1024 channels or fewer, but for spectrum with 2048 channels or more, smoothing helps to eliminate statistical fluctuations that might be confused with actual photopeaks. The program then performs a series of operations to locate peaks. The first of these operations is a five- point convolution method of calculating first derivatives for each channel. Then, by looking for sign changes in the first derivatives, the program locates possible peaks. 17 The program assigns the minimum on each side of the peak as the peak limits or boundaries. The program then checks to verify that the right hand boundary channel for the peak is not too far out. By comparing the left side derivatives to the right side derivatives, the right hand boundary channel is fixed. A baseline calculation is performed next, and then a few statistical tests of peak validity are done. The first test for a valid peak involves con— sideration of the following criterion: Peak Area > (5.0 x SIGMA) where peak area is total area minus base area, and SIGMA represents the standard deviation of the peak. The cal- culation of SIGMA is as follows: SIGMA - g D + (D + D ) [(R-LT1)2 - 1] " i L Rx-T' L where R represents the right hand boundary channel number, L represents the left hand boundary channel number, DL represents the number of counts in the left hand boundary channel, D represents the number of counts in the right R hand boundary channel, and Di represents the number of counts in the ith channel. The next test is used to eliminate Compton edges. The slope of the left side of the peak is compared to the slope of the right side of the peak. If the absolute 18 values of the slopes are within a factor of 1.5, the peak is passed to the baseline calculator. By inspection of Figure 2, one can see that a Compton edge would not pass the aforementioned "1.5“ test. Four channels to the outside of the peak boundaries are averaged, with those channels whose count is more than two standard deviations from the peak boundary channel count being disregarded. The right hand and left hand averages are taken as the counts in the boundary channels. The right hand and left hand boundary channels are straight-lined and a baseline is determined. The baseline is defined as the background level. Finally, the centroid of the peak is calculated. The user has the option of two different methods of determining peak intensity. The "Total Peak Area" method yields a peak intensity equal to the sum of the counts in the channels bounding the peak as determined by the statistical tests described above. This method uses the redefined counts in the boundary channels for sub- tracting out background. The second peak intensity method available is the "Wasson" method. In this method, the user specifies the number of channels to either side of the center channel of the peak to be used as the limits of integration. A baseline is determined as described above, but with the boundary channels as defined by the user, and the background is then subtracted out. 19 PHOTOPEAK COMPTON EDGE Figure 2.--Typical Photopeak and Compton Edge. 20 In order to calibrate the spectra (i.e.: assign energy values to each channel), reference and standard spectra must be provided to the program. First, a rough calibration is performed by using a 137Cs spectrum. 137C5 has a single peak located at 661.7 KeV. If photopeaks greater than 1836 Rev are to be located, a 88Y spectrum is also necessary, to assist the program in compensating for possible nonlinearity in the spectrometer. The refer- ence spectra addressed above may be deleted if the user supplies the program with the centermost channels for 137Cs and 88Y. Standard spectra are used next to give a precise calibration to the spectra. The user supplies the program with the energy levels of the gamma-rays in each standard spectrum. The program assigns the centroid of each peak located in the spectrum with the corresponding energy. Then the program determines energies for the photopeaks of the "unknown" sample spectra by interpola- tion assuming linearity between standard spectrum peaks. The program will not extrapolate energies above the highest standard peak supplied by the user. This completes the qualitative analysis portion of Spectra. Spectra is also capable of performing activation analysis calculations (or quantitative analysis). A flux monitor (i.e.: sample containing a known quantity of the element of interest) must be irradiated in the reactor in the same batch as the "unknown" samples. The user must 21 provide the program with the gamma ray energy of the element of interest, the chemical symbol, the half life of the isotope and the weight or concentration of the flux monitor sample. The user must also supply name of sample, weight of sample, time of day sample was counted and live time duration of count for each Spectrum used in the quan- titative analysis, both "unknowns" and "flux monitors." The program then uses the flux monitor spectra to calibrate each peak of interest. The "unknown" sample spectra are then analyzed for each peak of interest. Each peak is compared to the associated flux monitor peak and from sample weights the concentration of each element of interest is determined. In order to account for decay and live time the following formulae are used: Atl (flux monitor wt.) x (l - e- Formula 1: scr = {Peak area) x Ae Atz) where SCF is the standard comparator factor or the cal- ibration of the flux monitor peak, A is the decay constant for the isotope of interest, tl is the time elapsed between some reference time (e.g.: time of irradiation or time of first count in this analysis) and the start time of the counting of this spectrum, and t is the duration of the count (live time). 2 22 Formula 2: ACF = (peak area) X Ae-Atl (sample wt.) x (l - e-AtZ) where ACF is the analytical comparator factor, or the weighted intensity of the "unknown" sample peak of interest, and A, t1 and t2 are as described above, but evaluated for the "unknown." For a more detailed discussion of Spectra, see Appendix C. USER'S MANUAL This chapter describes the procedures for trans- ferring data for the ND analyzer to the IBM 1800 and for operating program Spectra. To transfer data to the IBM 1800, the ND analyzer, the "interface" and the IBM 1800 must be connected. The IBM 1800 must be cold started and program ND must be run. Once the data has been collected on data decks, the controls for Spectra must be prepared and finally Spectra is run. The procedure for these operations follows. Data Transfer Hook-Up (See Figure 3) (l) The following connections must be made: (a) The interface must be in a nimbin; (b) The cable from the back of the interface must be connected to the ND analyzer at "Printer A"; (c) The female single pin connection in the back of the interface must be connected to the ND analyzer at the point marked "complete"; (d) The cable from the IBM 1800 must be attached to the face of the interface; 23 24 68 69 DD El :24 IBM IBOO / lfl INTERFACE I PRINTER A l COgLETE L (REAR) NUCLEAR DATA ANALYZER Figure 3.--ND Analyzer--Interface--IBM 1800 Cable Hook-Ups. 25 (Note: the following connections are in the IBM 1800 room.) (a) Connect cable connectors marked "ND-68" and "ND-69" to the IBM 1800 at the digital inputs marked "68" and "69"; (b) Connect cable connector marked "ND—124" to the IBM 1800 at digital output "124". Cold Start of the IBM 1800 (l) (2) (3) (4) (5) (6) (7) (8) (9) (10) (ll) (12) (l3) (14) On console—~push POWER ON. On printer--push START. Place disk marked "Reactor Lab" in disk drive (middle slot). On disk drive--push START. Wait for READY light on disk drive. Place cold start card in hopper. On console--push IMMEDIATE STOP. On console--push and hold CLEAR STOR. On console--push START. On console-~release START and CLEAR STOR. On console-~push IMMEDIATE STOP. On card reader--push START. On console--push PROGRAM LOAD. Wait for cold start pattern. The cold start pattern appears on the operating console. Most of the small white lights will be lit except for four lights forming a square near 26 the center of the light panel. These are the lights corresponding to columns 9 and 10 in the adress register and I register rows. To Run ND (1) Prepare the following deck: (all cards begin in col. 1). //JOB /// XEQ ND FX (Note: FX begins in col. 16) blank card blank card (2) Place deck in hopper. (3) On card reader--push START. (4) ND is self-explanatory. The program will request information from the user on the IBM selectric terminal in the IBM 1800 room. Preparing to Run Spectra Note: For each "card" a format is prescribed. There are four types of formats, "A", "I", "F", and "X". Formats "A" and "I" have the following structure: nAm or nIm. The value of "n" gives the repetition number (e.g.: 3A2 is the same as A2, A2, A2). The value of "m" gives the number of characters allowed in the input field. The "A" format allows the input of alphanumeric characters (e.g.: A4 allows the input of TEST). The "I" format is used to input numeric data in integer form (whole numbers). Note that data in an "I" field must be right justified. If the data to be inputted in an 16 field is three digits 27 long, the three digits must be preceded by three blanks (e.g.: 126 in an 16 field must be bbb126, where b repre- sents blank). Format "X" has the following structure: nX. The "X" indicates a blanking format, where "n" is the number of blanks. The "F" format has a structure of: nFm.p where "n" is the repetition number, "m" is the total number of characters allowed in the input field, and "p" is the maximum number of digits to the right of the decimal point. The "F" format is used to input numeric data that is 293 whole number data. Note that the data need not be right justified in the input field, and that "m" includes the decimal point (e.g.: 125.89 requires a format of F6.2). In order to run Spectra, the following deck must be prepared: Card l--Format 416 columns l-6 (1) Number of standardizing spectra (including Cs and Y standards, if provided) columns 7-12 (2) Maximum energy of standard peaks (in Kev). columns 13-18 (3) Cs peak channel number (if spectrum provided, input "0") . columns 19-24 (4) Y peak channel number (if not used, input "0"). (Note: If max. energy of standards is greater than 1836.08 Kev, a Y spectrum or channel number is required.) 28 Card 2--Format 1216 (Multiple cards using the same format may be required, depending on the number of standard spectra used.) Cards with number of peaks in each standard. (Sequence must correspond with order in which standard spectrum are run. Not needed for Cs or Y data). Card 3—-Format 8F9.3 (Multiple cards using the same format may be required, depending on the total num- ber of peaks in the standard spectra used.) Cards with energies of peaks in each standard. (In the order in which they appear in the decks, i.e.: min. to max. for each spectrum in order.) Card 4--Format 316 and then 13A4 column 6 (l) "0" columns 7-12 (2) Number of channels in spectra columns 13-18 (3) Number of spectra to be analyzed (including flux monitors, but not stand- ards) columns 19-70 (4) Labels (run name). A maximum of 52 alpha— numeric characters are allowed. Card 5--Format 411 and then 116 column 1 (l) 0--raw data printed out l--raw data not printed out 29 column 2 (2) 0--smoothed data printed out l--smoothed data not printed out 2--smoothing operation omitted column 3 (3) 0--peak area by Wasson's method l--peak area by total peak area method column 4 (4) 0--activation analysis section used l-—activation analysis section not used columns 5-10 (5) Integer number of points on each side of the cen- ter channel, used for peak area. (Note: If card 5 col. 4 = l, omit card 6 and those following.) Card 6--Format 316 and then A4 columns 1-6 (1) Number of flux monitor spectra. (Note: multiple flux monitors have to have identical concentrations or quantities, only in different locations in reactor core during irradiation. The program does not accommodate different concentration flux monitors. Spectra merely averages the peak areas in multiple flux monitors.) columns 7-12 (2) Number of peaks to be analyzed. columns 13—18 (3) Amount of error in peak find--approximately three Kev (as recommended in the Baedecker write-up, see Appendix C.) columns Card 7--One columns columns columns columns columns columns 19-22 30 (4) Four alphanumeric charac- ters that identify the flux monitor spectra. for each peak analyzed 1-2 3-10 11-20 21-23 24-30 31-34 column 35 columns columns columns columns 36-40 41-50 51-56 57-60 (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) (11) Format A2--Chemical symbol being determined Format 8X--Space 8 Format F10.3--Energy of peak in Kev. Format 3X--Space 3 Format F7.3--Half—life Format 4X--Space 4 Format Al--Units of half- life (S,M,H,D,Y) Format 5X--Space 5 Format F10.5--Flux monitor weight or concentration Format 6X--Space 6 Format A4--Units of flux monitor weight or concen- tration (pg, m9, etc.) Card 8--One for each spectrum in deck (to be analyzed for activation analysis) columns columns 17-20 columns 21-30 1-16 (1) (2) (3) Format 4A4--Sample name (The program requires that the first four char- acters must be the same as in col. 19-22 if spectrum is to be treated as a flux monitor.) Format 4X-—Space 4 Format F10.5--Sample weight 31 columns 31-36 (4) Format 6X--Space 6 columns 37—40 (5) Format A4--Units of weight (ug, mg, etc.) columns 41-45 (6) Format 5X--Space 5 columns 46—48 (7) Format I3--hours, time of count, 2400 hour clock, if next day, add 2400 columns 49-50 (8) Format 12--Minutes columns 51-53 (9) Format 3X--Space 3 columns 54-59 (10) Format I6--Live time duration of count column 60 (11) Format Al--Units of time columns 61-64 (12) Format 4X--Space 4 Column 70 (13) Format I6--"0" Follow cards 1-8 with the data decks from the IBM 1800 as follows: (1) Cs spectrum if used; (2) Y spectrum if used; (3) Standard spectra; (4) Flux monitor spectra if doing activation analysis; (5) Unknown spectra. (Note: Place 789 multipunch card at the end of each spec- trum and place 6789 multipunch card at end of deck.) Running Spectra (1) Prepare the following deck (each card begins in col. 1) 32 PNC JOB CARD (Be sure to specify MTl to mount tape) PW= HAL, BANNER, SPECTRA. DISPOSE, **, V. APLIB, TT1313, *SPECLAB. MAP, OFF. SPECLAB. 789 (2) Follow this deck with the Spectra cards as described above. BIBLIOGRAPHY 33 BIBLIOGRAPHY General References Friedlander, G., Kennedy, J.W., and Miller, J.M. Nuclear and Radiochemistry. Second Edition, John Wiley and Sons, Inc. New York, N.Y., 1964. Foster, A.R. and Wright, R.L., Jr. Basic Nuclear Engineering. Third Edition, Allyn and Bacon, Inc. Boston, Mass, 1977. Gardner, R.P. and Ely, R.L., Jr. Radioisotope Measure- ment A lications in Engineering. Reinhold Pub- lisfiing Corp. New York, N.Y., 1967. Grouthamel, C.E., Adams, F. and Dams, R. Applied Gamma—Ray_Spectr9metry. Second Edition, Pergamon Press. Oxford, England, 1970. 34 APPENDIX A A LISTING OF PROGRAM ND 35 36 .m m_m.~.l._zz ..c_\.o fd+z<7ficz.uz .4_.»<11:d 9—K zqruz .mdm.c.:qma ...crz;l :_ 2. q_<: I: m4122 >b..\.»zz:: .m~«.c.:x:_q‘<_1xl dblv I: -._ L3 rqx::xa 11p..\..:Cx_ix~ Ir. :. 11~>ch < :2 Ire I:xl .\~....o > 4.3:. .cc..~_<»<:r ..c<~.~.<».¢c_:.«;_:.xc_:.gc_:..:~.14».p :Lclpz_ 44c pm_49 mxlcrpz_ :z:3 12:4 .31—_zila>p.;zc:r>lx.xm_;.:z:EE:: LmLm.~L:zz2: LmLm.cL:L :zc Lyn—m rm;I ZIIL .nzch 22L IhazLx:xaaa ILL: urLzza aIqux Equ wchuxIaazr IIL :q:L..\L~rr:: LmLm.xL:rz:: LmLm.cL:L 12¢ Lzapm qua zII» .m:xqu xZL ILaerzxaaq rLLx II;2:; aI;h 1C223C :: :qz 2L :IrLzza iqz_ :LLLIL uz:aLLLmn.cL: :LI |>iIa>L x234; ;; LIILz:a <»4:..\LL.«LILL:: LcLL. «EL.LLLLL>|2L11LLIL LLch<:z;I 2anLLme.cL:aI: LL-LLZ :— :I :2: z; LI> ;:I I>II1>~ 2I»1_:a mch II— a; #2: »Z_:a..\Lp<£::I chw.LLILLzs Lx_IE:: Lan.cL:ch L.n:LII;>L >;152: Lme.cL:L zlrp .I:;1 xIpsza Irp 2L n— ..x..rLLLax I::z yIL rmm 32L we: Lew CAM rcL 5c. nzL cc. me L:— Lcm IxzazL IIL Ixzx Ich :24 I::I »:;\LL :EI: Ire :P :z 21:»..prqraEI er :. L:<; 38 Z..—h<.:a.z:u 1:. 22% 3»:L tax::xa ca mLquL3<> a zzzzzu LLx¢zL sec z:xz:u :2 xzu mpzmszLzaua Luzu :¢::u:¢ Cn::ncL unccum :n::u:m Lm::n~ 1m:¢uc~ Lq:z z:u:; Lzz:x :wx:1 umzzm Lsz Lsz xL;_; ax:Cz p121 :LxL Lchm LaLLx :Lz:C uczzu C22aC xCxL: szza chz L: .cLC quasaxnxzm cLLLcL nuzL maqusz :azz L2: meu2aazzz :mpasaazm mua2hLm Jfi_:u oLm ezLCu an au:Cn an succ" er 44cc“ ch zcccu NLm L¢CCu .ch mzLLthCaaaq po1quhm nn::uL LLzeuz 4mcan LLcLC¢ mn:CuL LLsaaL mMCCuL LLuzzaL Lm::uL LLz :n::nL LLZLzzL L\;:uL LLw mecuL LLL :N:CuL LL; CA:Cu LLzaICZ :x::uL LLL <\;:uL LLx Jx::uL LLxu amczuL LL> FN:CuL LLch: (mesa. LLnsL: rmLLLLuL LLxLLLL {\LLLLHL ILLJ3 LLLLLLLImaLLLLuL L732» .CLLLLCnL aL>zxLLLL cchICnLLuLULLqpflL: cuCCICLCLuLULchqL: mZLC~hquLLLL< ”314—35., :2; thL LLqu ...::> x241» .cLLCLa:;C zLu: max chpsuLxL..\L» c ucccuw chcucL «cccum scccuLL «(CCuL mhquaz:u zu:Lth Lsz xLth quLz azsCx Lxxz x:»xL pszL :2cL mzqzazxaxzm :LLLqL meCLLZL 21:: L2: mxmuza;2:z :xha:a;:m muathlu L:L Lchu Lcn zuccu ch LJccu L u:::u ~ LNCCu ¢ m2:LL czC 2x:»C: 3cm Lqux.x~.¢L.xLL pczzzu ¢ LL.LuxL.Lz.LuLL.L~L.LLszquLL.¢zLLL¢.mL LpLaz Lem Len.:Cm.ccmLLucLLu_ C22L~2:u can Lzszzzu 3cm szLpz:u LcL 12L: «LL.LLLx2LzeL Lch.wL : zazzzu memzL :cc z:zzzu 9&LAL xzu mszzazL23C: Cazu loss": accencL :c::n» ccCCunL ILCqu :z Zanga :cm L Lchpr<:::C : LL.anL.L«.LuLL.LmL.LLLx2 a 221;:C LLxmzL : zczzzu 32L: xzu msztuzL20ua C::C 2L1:m micacszaz:m cLLLqu axCuLpzn :Lha3119 oLccu N m mz:LCz:u 1;: uaL»m :L:I L :Lm xsccch: L: st: (L LL: :zzL : (Le: éLzzzu 2L L1;Pm m¢z:C 2L2 x2; :rsL : «Le: mzL :Lx crx: : LL:: {L LL: ::xL : chc CLc:L paL>2;C 3L; 1:; cc:C c ass: .7: LL: hnx: c uccc LL<> L :Cm xcc::::: Lc Lac: ::L~ L :: cscccc¢u Lc «cc: max 2L mL aC~;:;C 3:2 xa::L c::L c occc Lme ~L x:L :qLLzchc LzL ~::: aszL: a: rLLm :.L: L x:z c::c::¢s Lc mccc xxx $.sz :mzx m xpv find; c .15: Lxx L1:Lx LLLax L va cnoc c «2:: xxLLchLz 3:4 L>z:: q stzL ::< rL<> :::.:L >1 >L1LLLzz xLLL an LLJL: ::< :L;z L>LL LLaL: LL: xCLa xxcx ;L:I zL 41:»n :Lzl xLLmLCanc :LzL LL: (L LLL >x >L3LLL:1 :LL FL;L: 1: xCL; xw L1» 2L zLx» chqaa< «qu r‘ ALLJL: sz>z:C q z:pp:1 :<:L LLc> xL<> :1L\ LELLLL xLIL— 1:;u azzL LI nzLLnL:Lx :uq LIL :<:L :L:x ::L<> 1L2 C1» szpm LL<> LL<> :L: LIL :;q LLq> 2;pr:1 :Lquz :c;L :sz LL L;:Lm LL<> 21:; La: :p LLLpzcu (L zLL >1 >LaLLLzz zLL L:L<> m:;L>Lza :<;L LL<> mrLLnLJLx :Iq LJLLm :.:I xch e xLzzL 1: xCL: xvcz 1x (7 1::L 4;waL>2:C ;: LLL 4 nLLcL: x:;L ;:L»:x L>qm :L:fl t 2...» .LLAILL‘L LLq prLa :LL and \\ .>szLn¢c L>:zq 2L vazxyL F‘N .J J-JJ—J—n‘; (\‘f\ .J-ld _I_l .J—l _J-l_£-J .JLJJ .J—J LLZ.‘ A L>qx :L:I :1L~ LzL 22 2: «xx Lax La::L L::: ~::: :32: x::: <::: :L~m LLLL \::c L::: L::c L::: :::: r¢Lr :::: :ccccqu CL:LCLXCCL :::c::rr :hcccch 7:cc::L¢ LLxh Lruuch: Lsz :xcq xhcc:ccx LLcL <5 CLLCLL¢Q :NCCCLLiL ::xL <~cc::¢u Lccc::L: Ccccc::u c:xL z::::::L L£::::¢: c~cc:::u :m:c::L¢ LLL» 1~:c::LC :c::::¢: qmcz :s:::::: :cc::::: ::xL ~¢3q 1ccc::¢L xch::LL: ¢¢3C L::L ::xL ¢:Lc asccccc: c:xL :2 3 LL E: —c —cc cc cc: H “F. F‘Fl “#4 “Aida-fl ~~~ CCCCCCCCCCCCCCCCCC: SCCC CCCCC u~:: cs:: 15:: (5:: ¢~:: m>:: Ls:: CC,LLC Lccc uc:c IcLLC chLLL OCLL: «cc: a::: s::: (ccc (as: c::: rcLLLL «0:: «c:: Lc:: chLC :cc: CPLLLC xnzc on:: p nLLc rncc cr:c arc: L A.LL: cncc C::c :iL: xq:c chLL KSLC he:: 4::: w::: «.15 L¢L:L urcc mec um:c cmc: am:c (me: wm:: mrc: Lac: Cnc: Lv:: uwcc 1x2: qwcc «we: c\:: wwc: excc rue: CLc: 2:L»L2:L 3:: :L 44 L 212LL1 :CL Lax meLa bl» AIL—mLJLx 3nd thLx slap r214; :wa ::L 2::LL1 1: mLLm c.:CL sz .L>dw aim» ”7C4; LLq meLo L221: znc \\ :LPLLaz:L z:L»uzzL a:: :u; .>sz2nm< L>:n< 2L mx:xxL :2 :2: chc L my: azLL ~33: «L:: L: 2: L22; : :L:: 9. LLL: : u::: L: z: :L:c L C::: L mm: :::: L::: L :mx ::::::L¢ L: x::: L ELL Lax ::::::2 LL: o::: L ::L xL::::LL L: ~::: ::L ::L: : <::: L x:2 ::::::¢~ L: «3:: me c:oc : r::: L :Lm AL::::L: L: L::: L: ::L :::: : :::: L2 :::<::n: c::: 45 «LL: L :L oLL::::L mzzx L :Lm <::::::: (L .LL: :3: «2:: L :Lm x:::::¢: ~2:x L < x:::::¢z 2 41¢. xLLxL mcL: L :L xLL:::¢: 4L LLa ::xL :zuw L :L >::::::u nnL 2:; 2L «2:: L :»w ::ccccc: LL m::Lm (L LL: ::xL qu :£_z L :»m L::::::: .32 2:a LIP LcL: L a oLL::::x AL 41m. uch mcL: L :L hLL::::L a:ux:<1 (L LL: ::xL 3L wi_L:.Lz ..L2Lxu :<:L L:L: LL x:L cLLcaxnc xzqz L :L x:::::¢u I~.:q:L L an; :ccccmLc 241C: L :L :14: L: 1::q mzqu :221: LL x:L ::cc:xnc xxx C> _.~:L.L 2L1:L >53; zmx 241:1 2140 meL 13.. XULIU 2419“ < ::I::2:; ><::< :xqu :zu~ LIL Lz: :zu~ :n ::quLzL :xzz 2::zcu mu xupzszo ::«u LIL C1LrI¢mm< $354 2— meinuL :2 :2; LLL: mm; 24IL2 L::: :LL: L: .2_L .:Lxm o ”LLL: mm: 2L: L::: 1LL: L: 241Lz :::: : 4LL: mm: 4JL: L::: oLL: mm; mcL: L::: «LL: max ~:L: L::: hLL: mm: L:L: L::: (LL: Q L: ::4: :::c : mLL: L: ::c: : 4LL: .C: :::: : mL L: L: 241:: :::c : «LL: ¢ma 1:22: L::: LLL: mm: L43: :.:c 2. NL:¢ : L::: :: L::m : L::: u: :::c c :::c mm; L2:z L::: L::: mm: ~22: L::: x::: APPENDIX B A LISTING OF PROGRAM SPECTRA 48 I5 08/15/77 01601.053 FY" ..600"I :l IHACE 091 73/7‘ SPLCYRI PDOCEIN 49 (\r 4 P\DFI1}f‘—nf\ Iroro-mnci’qhxi tutu: ~40 c-o-f‘ '- ou o—r. hera-cu osc1c—e.d*4r~clbcr O-onv- apnqur‘c (.1 r rcq ,. vo r-‘rcchcl '4‘ db“£fi u‘auqlhhhwhhhlph :cnILonntm a can nLc naouncal aaadooaooonfi on non onudmnnflnnn aoodannaL asp. mmm-ov.wm IV v; WWW .1»va mmwtrvszi .WWUJVIWMWIFWMV. v.90 Imam mmwtmmvwhmmm .v-v"... ..‘- 42.14.ch . '- O- 7 H U c: I... 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Iothuflz to. -II I I:- ..u cm c-wau :Ir¢;ur IN n. ccmcu raspga a" mcmcu an r 47 -IIII-I-IILm - grid - - - - - II IIIIII tivrlt I953; 553..» r... be». I u q? ocur nnquuz on r" n4wuu u:r~»2ou '— o— ncmuu I nuo:ux IIII-lII- i or} I BJrIbiI-I I -II I III-- -I- II I - I --c~-.pr..cn8.¥.-C=c255act: N. n¢uru -~cm.rcthu 9 —p o¢m¢u A.«ouuv.afiozecp¢o—v.mov.a (5.0 x SIGMA) The primary purpose of the next test is to elim- inate Compton edges, but it is also useful in eliminating spurious peaks which get by the first test. The maximum first derivative is located on the left side of the peak, the minimum derivative on the right. This gives a measure of the slope at the point of inflection on each side of 74 the peak. The absolute values of the slopes are then compared to see that they are the same within a factor of 1.5. After a peak has passed the previous two tests, a linear baseline is defined for the photopeak. Several channels on each side of the peak are used to define the background. Four channels to the left of the left peak limit are examined. Those channels which have the same total accumulated counts as the left hand boundary channel (within two standard deviations) are averaged and this average is taken as a new value for the counts accumulated at the left hand peak limit and used to define the back- ground. The process is repeated on the right hand side of the photopeak. The baseline is then a straight line drawn between the two boundary channels. The centroid of the peak is determined next using seven channels (three on each side of the channel with the greatest number of counts) using the method of Savitzky and Golay. Two methods for measuring the intensity of the peak are built into the program, to be selected by the user. These methods are discussed in Appendix A, where they are referred to as the "Total Peak Area Method" and the "Wasson Method." In the total peak area method, the area is calculated as for the statistical test above, but using the redefined values for the boundary channels. In 75 the Wasson method a number of channels, specified by the user, are taken as the limits of integration. The base- line is determined as above, and using that baseline, background is subtracted from the channels within the selected limits for integration. The peak area is cal- culated as: Base Area = (Bl + Br) x (X + 0.5) l+X 2 Di - base area l-X Peak Area where l = centermost channel x = number of channels on each side of centermost channel to be included in peak area determina- tion D.= number of counts in ith channel B and Br = calculated values for the background 1 in channels l-X and 1+x respectively, computed from a straight line drawn between the peak limits 1+x A 2 SIGMA = 2 Di + (B1 + Br) x (x + 0.5) l-x The program will determine the energies of the photopeaks from their centroids, provided spectra of gamma- ray standards are included on the input tape. If the energies are to be determined, the first spectrum on the 137 tape should be a Cs spectrum. This spectrum serves as 76 a reference spectrum to provide an approximate energy calibration for locating peaks of known energy in the standard spectra. Due to possible nonlinearity in the spectrometer, 88Y must be provided as a second reference spectrum if any of the photopeaks used as standards have energies greater than 1836 Rev (the Cs and Y reference spectra may be deleted providing the centermost channels for the Cs (and Y) peaks are included as input data on the first data card). Following the reference spectra on the tape, up to 20 spectra of standards may be used to obtain the energy. calibration of spectrometer. The energies of the gamma- rays in each standards spectrum are read in on data cards and the correspondong centroids are determined. Up to 50 lines may be used in the standards spectra. The program determines the gamma-ray energies in all subsequent spectra by interpolation, assuming that the energy calibration is linear between standard lines. The program does not extrapolate beyond the highest energy of the gamma-ray standards. When the program is used to process spectral data from an activation analysis experiment, the energies of the gamma-ray lines to be used in the analyses are read in on one set of data cards. Along with the gamma-ray energy, the chemical symbol of the element to be determined, the half-life of the radioisotope used and the weight (or 77 concentration) of the element in the flux monitor are included on the data card. A second set of data cards (one card for each spectrum on the tape) provides the following information: (1) the name of the sample; (2) the weight of the sample: (3) the units in which the sample weight is expressed; (4) the time of day the sample was counted; (5) the live-time duration of the count. If the weights of the elements in the flux monitors are constant from flux monitor to flux monitor, they may be entered in the appropriate field on the first set of data cards, and no sample weights entered for the flux monitors in the second set of data cards. If the flux monitors used are standard powders or solutions, the concentrations of the elements in the standard powder or solution may be placed on the first set of data cards, and the weights of the standard powders or solutions entered in the sample weight field on the second set of data cards. The program first makes a pass through the spectra on the tape and analyzes the flux monitor spectra. It picks out the peaks of interest in each flux monitor spectrum and calculates the "standard comparator factor" for each peak. After all flux monitor spectra have been analyzed (the program can process up to ten), the standard comparator factors for each peak are averaged to yield an "average standard comparator factor" for each peak, which 78 is used to calculate concentrations when the sample spectra are analyzed. The tape is now backspaced to the first spectrum for the activation analysis run under consideration (there may be more than one run on a given reel of tape). Each sample spectrum is then analyzed in turn, an "analyt- ical comparator factor" calculated for each peak of interest, and, from the average standard comparator factors previously calculated, concentrations are calculated for the elements of interest in the sample. The standard deviation for the concentration is calculated based on counting statistics alone. In an activation analysis experiment involving the counting of short-lived nuclides, one flux monitor may be irradiated and counted for each sample analyzed. The program will handle this as a special case, as follows: in an activation analysis run a card is provided which tells the computer how many flux monitor spectra are in a given run. If this number is put to less than zero, the program expects that every other spectrum will be a flux monitor spectrum, and that each sample spectrum will follow its corresponding flux monitor spectrum on the tape. If, for some reason, no flux monitors were count- ing during an activation analysis run, the number of flux monitor spectra can be put equal to zero on the data card 79 and the program will process the spectra and calculate analytical comparator factors for each peak in each sample spectrum. In calculating standard comparator factors and analytical comparator factors, the program corrects the counting data for decay during the count and corrects each count for decay back to the time of the start of the first count in the activation analysis run. That is: SCF = (peak area) x Aektl (flux monitor weight) x (l - e-Ata) Atl ACF = (peak area) x Xe (sample weight) x (l - e-Xta) where t1 = the elapsed time between the start of the first count in the experiment and the start of the count being processed ta = duration of the count (live time) The program operates on various different levels of complexity, determined by the input data cards. It can simply read spectra and analyze the spectral data. On another level the program will determine the energies of the photopeaks in the spectra, provided appropriate standard spectra are provided. Thirdly, the program can process spectral data from an activation analysis experi- ment and calculate element concentrations. Some output Table l.—-Gamma 80 Rays Used as Primary Energy Standards. Source Energy (keV) Source Energy (keV) 241AM 59.536 1 0.001 19211 468.060 1 0.010 1°9Cd 88.034 1 0.010 Annihilation 511.003 1 0.002 182Ta 100,106 1 0.001 20781 569.690 1 0.030 5706 122.046 1 0.020 2OBTI 583-139 i 0-023 144Ce 133.503 1 0.020 1921r 604-378 i 0-020 57Co 135,465 1 0.020 19211 612.430 1 0.020 141Ce 145.442 1 0.010 137Cs 661-615 i 0-030 182Ta 152.435 1 0.004 54Mn 834-840 i 0-050 139Ce 165.852 1 0.010 88Y 898-023 i 0-065 182Ta 179.393 1 0.003 20781 1063-635 i 0-040 182Ta 222.110 1 0.003 60Co 1173.231 1 0.030 lepb 233,524 1 0,003 22Na 1274.550 1 0.040 203Hg 279.179 1 0.010 6OCo 1332.508 1 0.015 19211 295.938 1 0.010 l4°La 1596-200 1 0-040 19211 303,440 1 0.010 1248b 1691.022 1 0.040 19211 316.490 1 0.010 88Y 1836-127 i 0-050 131I 364.491 1 0,015 20811 2614.708 1 0.050 198Au 411.792 1 0.008 24Na 2754-142 i 0-050 81 options are included in the program in that the user can tell the program whether or not to print out the raw spectral data and whether or not to print out the smoothed data. The following data cards must be provided by the user . Card Format 1 Card with number of reference and stand- 416 ards spectra on tape, and the maximum gamma- ray energy of standard lines. The centermost channels of the Cs (and Y) peaks may be included on this card if the gamma-ray energies are to be determined and the Cs (and Y) reference spectra are left off the input tape. IF THE NUMBER OF STANDARDS SPECTRA IS ZERO, OMIT CARDS 2 AND 3. 2 Cards with the number of photopeaks in 1216 each standards spectrum. 3 Cards with the energies of the photo- 8F9.3 peaks in each standards spectrum in the order that the spectra appear on the tape. 4 Card with number of Spectra to be 316, skipped, size of spectra, number of 13A4 spectra (not including reference and 82 Card Format standard spectra or any spectra to be skipped following the first spectrum in an activation analysis run), and labels. 5 Card which controls various options built 4Il,I6 into program. The first four columns con- trol the operation of the program. Column l--zero-raw data printed out one-raw data not printed out Column 2--zero-smoothed data printed out one-smoothed data not printed out two-smoothing operation deleted Column 3--zero-peak area integrated by Wasson's method one-peak integrated to give total peak area Column 4--zero-program will calculate elemental concentrations from activation analysis data one-activation analysis program bypassed Column 5--lO-—integer number of points on each side of center channel to be included in peak area determined by Wasson's method 83 Card Format Cards 4 and 5 may be repeated together any number of times. If there is more than one run per tape, place a card with a negative number (I6 format) between each set of data cards. 6 If column 4 of card 5 is l, omit this and the following data cards: Card with number of flux monitor spectra 216,5Al, on tape and number of peaks in spectra A4 which are to be analyzed. Columns 13-17 must have the letters SMHDY in that order. Columns 18-21 must have the first four char- acters to be used in the sample name field on cards described under 8 below, which iden- tify the flux monitor spectra. The card for each flux monitor spectrum must have the first four characters in the sample name field, identical to the listed characters. 7 Set of cards, one for each peak to be A2,BX, F10, 3’ analyzed. Each card must have: 3X, F7, 3' 4X, a. chemical symbol for element being Al, 5X determined using given photopeak F10, 5, 6X, A4 b. energy of photopeak in KeV c. radioisotope half-life d. units in which half-life is expressed (S seconds, M = minutes, H = hours, D days, Y = years) Card 8 84 Format e. flux monitor weight or concentration f. units in which flux monitor weight is expressed (mg, mg, etc.) ug, mg Set of cards, one for each spectrum on 4A4, 4X, F10.5, tape in order of spectra appearance on 6X, A4, 5X, I3, tape. Each card must have: 12, 3x, 16, A1, a. sample name 4X, I6 b. sample weight c. sample weight units (GRAM, Mg, etc.) d. time of day count started--8:30 PM would be represented as 2030. If an activation analysis experiment runs into another day, time of second day starts at 2400 (e.g., 1:00 AM would be 2500) ‘ e. live time duration of count f. live time units 9. spectra to be skipped after processing spectrum described by card. (.1! llifylllllillilul ‘.|l(lvi I... \ 5471.11,...“ :.l"..l||‘l.‘u '01.|1£.¢fl1 ’ MICHIGAN STnTE UNIV.ILIBR9RIES ‘ll(“IIIIIWIMIWWWW“VWIHWIWWI 31293007092863