=======================================================================
Fixup

Fixup

PROGRAM
FIXUP
Fixup

VERSION 84-1
(NOVEMBER 1984)
Fixup

VERSION 86-1
(JANUARY 1986) *IMPROVED BASED ON USER COMMENTS       Fixup

*FORTRAN-77/H VERSION
Fixup

VERSION 86-2 (JUNE
1986)    *ALLOW CREATION
OF SECTIONS OF CROSS
Fixup

SECTIONS WHICH ARE NOT PRESENT IN     Fixup

THE ORIGINAL EVALUATION
Fixup

VERSION 88-1
(JULY 1988)
*OPTION...INTERNALLY DEFINE ALL I/O    Fixup

FILE NAMES (SEE, SUBROUTINE FILEIO    Fixup

FOR DETAILS).
Fixup

*IMPROVED BASED ON USER COMMENTS.      Fixup

VERSION 89-1
(JANUARY 1989) *PSYCHOANALYZED BY PROGRAM FREUD TO    Fixup

INSURE PROGRAM WILL NOT DO ANYTHING   Fixup

CRAZY.
Fixup

*UPDATED TO USE NEW PROGRAM CONVERT    Fixup

KEYWORDS.
Fixup

*ADDED LIVERMORE
CIVIC COMPILER
Fixup

CONVENTIONS.
Fixup

VERSION 89-2
(MARCH 1989)   *ADDED ENDF/B-VI
SUMMATION RULES AND   Fixup

DEFINED MF AND MT NUMBERS. PROGRAM    Fixup

WILL NOW USE MF=1, MT=451 TO DEFINE   Fixup

THE ENDF/B FORMAT OF THE DATA (E.G.,  Fixup

ENDF/B-VI OR EARLIER) AND USE THE     Fixup

CORRECT SUMMATION RULES FOR EACH      Fixup

VERSION OF THE ENDF/B FORMAT. IF      Fixup

MF=1, MT=451 IS NOT PRESENT PROGRAM   Fixup

WILL
USE ENDF/B-VI SUMMATION
Fixup

CONVENTIONS AS A DEFAULT.
Fixup

VERSION 90-1
(JUNE 1990)    *UPDATED
BASED ON USER COMMENTS
Fixup

*ADDED
PHOTON INTERACTION, MF=23       Fixup

VERSION 91-1
(JUNE 1991)    *ADDED
FORTRAN SAVE OPTION
Fixup

*NEW MORE CONSISTENT ENERGY OUTPUT     Fixup

ROUTINE
Fixup

VERSION 92-1
(JANUARY 1992) *ADDED OPTION TO CALCULATE RATIOS,     Fixup

E.G., CAPTURE/FISSION AND PRODUCTS,   Fixup

NU-BAR*FISSION - AND OUTPUT THE       Fixup

RESULTS IN THE ENDF/B FORMAT (SEE,    Fixup

BELOW - CREATING RATIOS AND PRODUCTS) Fixup

*ALLOW TOTAL NU-BAR (MF=1, MT=452) TO  Fixup

BE USED IN DEFINING RATIOS OR
Fixup

PRODUCTS.
Fixup

*ALLOW ALL CROSS SECTIONS TO BE PUT    Fixup

ON A UNIFORM ENERGY GRID.
Fixup

*NOTE, CHANGE IN INPUT FORMAT FOR      Fixup

RANGES OF MT NUMBERS
Fixup

*COMPLETELY CONSISTENT I/O ROUTINES -  Fixup

TO MINIMIZE COMPUTER DEPENDENCE.      Fixup

VERSION 93-1
(JULY 1993)    *CORRECTED
ALGORITHM TO CREATE UNIFORM Fixup

ENERGY GRID.
Fixup

VERSION 94-1
(JANUARY 1993) *VARIABLE ENDF/B DATA FILENAMES
Fixup

TO ALLOW ACCESS TO FILE STRUCTURES    Fixup

(WARNING
- INPUT PARAMETER FORMAT
Fixup

HAS BEEN CHANGED)
Fixup

*INCREASED PAGE SIZE FROM 1002 TO      Fixup

12000
DATA POINTS.
Fixup

*CLOSE ALL FILES BEFORE TERMINATING    Fixup

(SEE, SUBROUTINE ENDIT)
Fixup

VERSION 96-1
(JANUARY 1996) *COMPLETE RE-WRITE
Fixup

*IMPROVED COMPUTER INDEPENDENCE
Fixup

*ALL DOUBLE PRECISION
Fixup

*ON SCREEN OUTPUT
Fixup

*UNIFORM TREATMENT OF ENDF/B I/O       Fixup

*IMPROVED OUTPUT PRECISION
Fixup

*DEFINED SCRATCH FILE NAMES
Fixup

*INCREASED PAGE SIZE FROM 12000 TO     Fixup

36000 DATA POINTS.
Fixup

VERSION 99-1
(MARCH 1999)   *CORRECTED
CHARACTER TO FLOATING       Fixup

POINT READ FOR MORE DIGITS
Fixup

*UPDATED TEST FOR ENDF/B FORMAT
Fixup

VERSION BASED ON RECENT FORMAT CHANGE Fixup

*GENERAL IMPROVEMENTS BASED ON
Fixup

USER FEEDBACK
Fixup

VERSION 99-2
(JUNE 1999)    *ASSUME
ENDF/B-VI, NOT V, IF MISSING
Fixup

MF=1, MT-451.
Fixup

*FIXED CREATION OF SECTIONS
Fixup

VERS. 2000-1
(FEBRUARY 2000)*GENERAL IMPROVEMENTS BASED ON
Fixup

USER
FEEDBACK
Fixup

VERS. 2002-1
(MAY 2002)
*OPTIONAL INPUT PARAMETERS
Fixup

*SUMMATION RULES ARE DEFINED BASED     Fixup

ON
CONTENTS OF TABLES.
Fixup

VERS. 2004-1
(JAN. 2004)    *GENERAL
UPDATE BASED ON USER FEEDBACK Fixup

*INCREASED PAGE SIZE FROM 36000 TO     Fixup

60000
DATA POINTS.
Fixup

VERS. 2005-1
(JAN. 2005)    *UPDATED MT
CREATION TO ALLOW MAT =0
Fixup

INDICATING CREATE FOR ALL MATS.       Fixup

VERS. 2007-1
(JAN. 2007)    *CHECKED
AGAINST ALL ENDF/B-VII
Fixup

*INCREASED PAGE SIZE FROM 60,000 TO    Fixup

600,000 DATA POINTS.
Fixup

Fixup

OWNED,
MAINTAINED AND DISTRIBUTED BY
Fixup

------------------------------------
Fixup

THE NUCLEAR DATA
SECTION
Fixup

INTERNATIONAL
ATOMIC ENERGY AGENCY
Fixup

P.O. BOX
100
Fixup

A-1400, VIENNA,
AUSTRIA
Fixup

EUROPE
Fixup

Fixup

ORIGINALLY
WRITTEN BY
Fixup

------------------------------------
Fixup

DERMOTT E.
CULLEN
Fixup

UNIVERSITY OF
CALIFORNIA
Fixup

LAWRENCE LIVERMORE
NATIONAL LABORATORY
Fixup

L-159
Fixup

P.O. BOX
808
Fixup

LIVERMORE, CA
94550
Fixup

U.S.A.
Fixup

TELEPHONE  925-423-7359
Fixup

E. MAIL    [email-masked]
Fixup

WEBSITE
HTTP://WWW.LLNL.GOV/CULLEN1
Fixup

Fixup

PURPOSE
Fixup

=======
Fixup

THIS PROGRAM IS
DESIGNED TO READ EVALUATED DATA IN THE ENDF/B      Fixup

FORMAT, PERFORM
CORRECTIONS AND OUTPUT THE RESULT IN THE ENDF/B    Fixup

FORMAT. TWO
TYPES OF CORRECTIONS ARE POSSIBLE (1) AUTOMATIC AND    Fixup

(2) OPTIONAL
(BASED ON USER INPUT) CORRECTIONS.
Fixup

Fixup

ONE OF THE MOST
IMPORTANT FUNCTIONS OF THIS PROGRAM IS TO
Fixup

RE-DEFINE ALL
REDUNDANT CROSS SECTIONS (E.G. TOTAL) TO BE EXACTLY  Fixup

EQUAL TO THE SUM
OF ITS PARTS. THIS PROCEDURE ELIMINATES THE       Fixup

PROBLEM WITH
MANY ENDF/B EVALUATIONS, WHERE DUE TO THE USE OF      Fixup

NON-LINEAR
INTERPOLATION LAWS THE TOTAL MAY BE EQUAL TO THE SUM    Fixup

OF ITS PARTS AT
ALL TABULATED ENERGIES, BUT BASED ON THE
Fixup

INTERPOLATION
LAWS IT CAN BE QUITE DIFFERENT AT ENERGIES BETWEEN   Fixup

TABULATED
ENERGIES.
Fixup

Fixup

AUTOMATIC
CHECKS/CORRECTIONS
Fixup

============================
Fixup

(1) CHECK THAT
MAT/MF/MT DOES NOT CHANGE UNLESS A MEND/FEND/SEND   Fixup

LINE IS READ. IF MAT/MF/MT CHANGES A WARNING MESSAGE IS
Fixup

PRINTED BUT NO CORRECTIVE ACTION IS TAKEN.
Fixup

(2) ALL LINES
WITHIN A GIVEN MAT WILL BE SEQUENTIALLY NUMBERED     Fixup

ON OUTPUT.
Fixup

Fixup

OPTIONAL
CHECKS/CORRECTIONS
Fixup

===========================
Fixup

THE FOLLOWING
NUMBERS CORRESPOND TO THE INPUT DATA OPTION COLUMNS  Fixup

(SEE THE
DESCRIPTION OF THE INPUT BELOW)
Fixup

Fixup

(1) CORRECT ZA
AND AWR IN ALL SECTIONS. CHECK TO INSURE THAT THE   Fixup

C1 AND C2 VALUES (ZA AND AWR) ARE THE SAME IN ALL SECTIONS.    Fixup

THE C1 AND C2 OF THE FIRST SECTION READ ARE ASSUMED TO BE      Fixup

CORRECT AND ARE USED FOR COMPARISON. IF THE C1 AND/OR C2 OF    Fixup

THE FIRST SECTION ARE NOT POSITIVE AN ERROR MESSAGE IS OUTPUT  Fixup

AND THE MATERIAL IS COPIED WITHOUT CHANGE.                     Fixup

NOTE....TO CHANGE THE ZA AND/OR AWR OF ANY MATERIAL IT IS      Fixup

MERELY NECESSARY TO CHANGE THE ZA AND/OR AWR IN THE FIRST      Fixup

SECTION OF THE MATERIAL AND USE THIS OPTION TO AUTOMATICALLY   Fixup

CHANGE ALL OTHER SECTIONS.
Fixup

(2) CORRECT
CROSS SECTION (MF=3) THRESHOLDS. THE Q-VALUE AND AWR   Fixup

ARE USED TO DERIVE THE REACTION THRESHOLD USING THE RELATION,  Fixup

Fixup

E-THRESHOLD = -(Q-VALUE)*(AWRE+1.0)/AWRE
Fixup

Fixup

IF THE THRESHOLD IS POSITIVE THE
CROSS SECTION IS CHECKED TO
Fixup

INSURE THAT THE FIRST TABULATED POINT IS AT THE THRESHOLD AND  Fixup

HAS A ZERO CROSS SECTION. IF NOT, THE CROSS SECTION WILL BE    Fixup

CHANGED.
Fixup

(A) IF THE FIRST TABULATED POINT IS ABOVE THE THRESHOLD AND    Fixup

HAS A ZERO CROSS SECTION, THE POINT IS DELETED AND A POINT Fixup

IS INSERTED AT THE THRESHOLD.
Fixup

(B) IF THE FIRST TABULATED POINT IS ABOVE THE THRESHOLD AND    Fixup

HAS A NON-ZERO CROSS SECTION, A POINT WITH ZERO CROSS      Fixup

SECTION IS INSERTED AT THE THRESHOLD.
Fixup

(C) IF THE FIRST TABULATED POINT IS BELOW THE THRESHOLD AND    Fixup

HAS A NON-ZERO CROSS SECTION, ALL POINTS BELOW THE
Fixup

THRESHOLD ARE DELETED AND A POINT WITH ZERO CROSS SECTION  Fixup

IS INSERTED AT THE THRESHOLD.
Fixup

(3) EXTEND ALL
CROSS SECTIONS (MF=3) TO 20 MEV. IF THE TABULATED   Fixup

CROSS SECTION ENDS BELOW 20 MEV IT WILL BE EXTENDED TO 20 MEV  Fixup

AS EITHER ZERO (IMOPS(3)=1) OR CONSTANT (IMOPS(3)=2) EQUAL     Fixup

TO THE LAST TABULATED VALUE.
Fixup

(4) ALLOW
REACTION (MF=3, ANY MT) DELETION. ALL SPECIFIED          Fixup

REACTIONS WILL BE DELETED WHEN THE DATA IS READ FROM THE       Fixup

INPUT ENDF/B DATA FILE AND WILL NOT BE IN THE OUTPUT ENDF/B    Fixup

DATA FILE. WARNING DELETED REACTIONS MAY NOT BE USED TO DEFINE Fixup

ANY RECONSTRUCTED REACTIONS (I.E. REACTIONS DEFINED BY SUMMING
Fixup

OTHER REACTIONS). SINCE DELETED REACTIONS ARE DELETED DURING   Fixup

READING IT IS AS IF THEY NEVER EXISTED AND IF ANY DELETED      Fixup

REACTION IS REQUIRED
LATER TO DEFINE ANY SUM AN ERROR WILL     Fixup

RESULT. THE USER MAY SPECIFY THAT THE DELETION RULES ARE TO BE
Fixup

READ FROM INPUT (IMOPS(4)=1) OR THAT THE BUILT IN SUMMATION    Fixup

RULES ARE TO BE USED (MOPS(4)=2). AT THE PRESENT TIME THE      Fixup

BUILT-IN DELETION RULES ARE THAT NO SECTIONS SHOULD BE DELETED
Fixup

(THE USER MAY OVERRIDE THIS CONVENTION BY INPUT).
Fixup

(5) ALLOW
REACTION (MF=3, ANY MT) RECONSTRUCTION BY SUMMING OTHER  Fixup

REACTIONS. IN ORDER TO OPTIMIZE THE RUNNING TIME OF THIS       Fixup

PROGRAM CARE SHOULD BE EXERCISED TO MINIMIZE THE NUMBER OF     Fixup

TIMES THAT EACH CONTRIBUTING CROSS SECTION MUST BE USED.       Fixup

THE USED MAY SPECIFY THAT THE SUMMATION RULES ARE TO BE READ   Fixup

AS INPUT (IMOPS(5)=1) OR THAT THE BUILT IN SUMMATION RULES     Fixup

ARE TO BE USED (IMOPS(5)=2). THE BUILT IN SUMMATION RULES ARE  Fixup

DESIGNED TO USE ENDF/B CONVENTIONS AND TO MINIMIZE THE NUMBER  Fixup

OF TIMES THAT EACH CROSS SECTION IS USED.
Fixup

(6) INSURE THAT
ALL CROSS SECTIONS ARE NON-NEGATIVE (I.E. ARE      Fixup

ZERO OR POSITIVE). DURING READING ALL NEGATIVE CROSS SECTIONS  Fixup

WILL BE SET EQUAL TO ZERO AND TREATED AS SUCH DURING ALL       Fixup

SUBSEQUENT SUMMATIONS AND ENDF/B OUTPUT.
Fixup

NOTE...THIS OPTION SHOULD NEVER BE USED WITH DATA CONTAINING   Fixup

BACKGROUND CROSS SECTIONS WHICH MAY BE NEGATIVE. ONLY AFTER    Fixup

THE RESONANCE CONTRIBUTION HAS BEEN ADDED TO THE BACKGROUND    Fixup

TO DEFINE THE ACTUAL CROSS SECTION IS IT VALID TO ELIMINATE    Fixup

NEGATIVE CROSS SECTIONS.
Fixup

NOTE...THIS OPTION MAY BE USED TO DELETE NEGATIVE ELASTIC      Fixup

CROSS
SECTIONS THAT MAY RESULT FROM RECONSTRUCTING CROSS       Fixup

SECTIONS FROM SINGLE LEVEL BREIT-WIGNER PARAMETERS. IF THE     Fixup

TOTAL CROSS SECTION IS THEN RECONSTRUCTED USING THE CORRECTED  Fixup

ELASTIC CROSS SECTION THE TOTAL WILL BE POSITIVE DUE TO THE    Fixup

CONTRIBUTIONS OF CAPTURE AND FISSION (THUS AVOIDING NUMERICAL  Fixup

INSTABILITY PROBLEMS DURING SELF-SHIELDING CALCULATIONS).      Fixup

(7) WITHIN EACH
SECTION OF CROSS SECTIONS DELETE ENERGIES THAT     Fixup

ARE NOT IN ASCENDING ENERGY ORDER (ENERGY REPETITION IS O.K.)  Fixup

(8) WITHIN EACH
SECTION OF CROSS SECTIONS ELIMINATE DUPLICATE      Fixup

POINTS (SUCCESSIVE POINTS WITH THE SAME ENERGY-CROSS SECTION).
Fixup

(9) TEST THAT
ALL SECTIONS ARE IN ASCENDING MAT/MF/MT ORDER.       Fixup

IF NOT, NO CORRECTIVE ACTION WILL BE TAKEN, ONLY AN ERROR      Fixup

MESSAGE WILL BE OUTPUT.
Fixup

(10) CHECK MF/MT FOR
EACH SECTION TO INSURE THAT THEY ARE DEFINED   Fixup

IN THE ENDF/B FORMAR MANUAL. IF THEY ARE NOT DEFINED AN ERROR  Fixup

MESSAGE IS PRINTED, BUT NO CORRECTIVE ACTION IS TAKEN.
Fixup

(11) ALLOW SECTIONS
WHICH ARE NOT PRESENT IN THE ORIGINAL (INPUT)   Fixup

EVALUATION TO BE CREATED. NORMALLY THIS PROGRAM WILL ONLY      Fixup

RECONSTRUCT AND OUTPUT SECTIONS IF THE SECTION IS PRESENT      Fixup

IN THE ORIGINAL EVALUATION. THIS PROCEDURE IS FOLLOWED BECAUSE
Fixup

NORMALLY THE PROGRAM DOES NOT KNOW HOW TO DEFINE THE CONTENTS  Fixup

OF THE FIRST TWO LINES OF THE SECTION (E.G., Q-VALUE,
Fixup

TEMPERATURE, INITIAL AND FINAL STATES). THIS OPTION MAY BE     Fixup

USED TO ALLOW THE PROGRAM TO READ AND SAVE A TABLE DEFINING    Fixup

THE CONTENTS OF THE FIRST TWO LINES OF EACH SECTION TO BE      Fixup

CREATED.
Fixup

NOTE...IF A SECTION IS PRESENT ANY COMMAND TO CREATE IT WILL   Fixup

BE IGNORED.
Fixup

(12)ALLOW ENERGY
POINTS TO BE INSERTED. THE PROGRAM CAN READ UP    Fixup

TO 50, ENERGIES, MAT, MT AND USE LINEAR INTERPOLATION TO       Fixup

INSERT ENERGY POINTS INTO TABLES AS THEY ARE READ, E.G.,       Fixup

INSERT AN ENERGY POINT AT THERMAL ENERGY (0.0253 EV). IF       Fixup

AN MAT AND/OR MT IS ZERO THIS IMPLIES = ALL - INSERT THE       Fixup

ENERGY IN ALL TABLES.
Fixup

(13)PUT ALLOW
CROSS SECTIONS ON A UNIFORM ENERGY GRID = EACH       Fixup

SECTION (MT) OF CROSS SECTIONS WILL INCLUDE ALL ENERGIES       Fixup

WHICH APPEAR IN AT LEAST ONE SECTION OF DATA. PARAMETERS       Fixup

(MT=251 THROUGH 255) ARE NOT INCLUDED IN THE UNIFORM ENERGY    Fixup

GRID.
Fixup

(14)DELETE
SECTION IF CROSS SECTION = 0 AT ALL ENERGIES. THIS      Fixup

SOUNDS LIKE AN ABSURD OPTION, BUT IS REQUIRED BECAUSE SUCH     Fixup

SECTIONS EXIST IN ENDF/B-VI.
Fixup

Fixup

CREATING RATIOS
AND PRODUCTS
Fixup

============================
Fixup

IN ORDER TO
CREATE RATIOS AND PRODUCTS = NEW MT NUMBERS, YOU MUST  Fixup

DO TWO
THINGS,
Fixup

Fixup

1) DEFINE EACH
NEW MT NUMBER AS A RATIO OR PRODUCT OF TWO MT       Fixup

NUMBERS.
Fixup

Fixup

2) USE THE
CREATE MT NUMBER OPTION AND INPUT THE FIRST TWO LINES   Fixup

OF THE SECTION
Fixup

Fixup

WARNING - UNLESS
YOU DO BOTH OF THESE YOU WILL NOT OBTAIN OUTPUT   Fixup

IN THE ENDF/B
FORMAT.
Fixup

Fixup

TWO SPECIAL MT
NUMBERS HAVE BEEN DEFINED BY CSEWG INVOLVING
Fixup

RATIOS AND
PRODUCTS,
Fixup

Fixup

ALPHA (MT=254)=
CAPTURE (MT=102)/FISSION (MT=18)
Fixup

Fixup

ETA
(MT=255)  = NU-BAR (MT=452)*FISSION
(MT=18)/ABSORPTION (MT=27) Fixup

Fixup

ABSORPTION
(MT=27) = FISSION (MT=18) + SUM (MT=102 THROUGH 116)    Fixup

Fixup

AS YET THERE IS
NO STANDARD DEFINITION OF MT NUMBERS FOR RATIO     Fixup

OR PRODUCT DATA.
YOU ARE FREE TO USE ANY MT NUMBERS NORMALLY NOT   Fixup

USED IN THE
ENDF/B. HOWEVER, IT WILL THEN BE YOUR RESPONSIBILITY   Fixup

TO PROPERLY
INTERPRET THE RESULTS, I.E., NOBODY ELSE WILL HAVE     Fixup

ANY IDEA HOW TO
INTERPRET A TABLE OF DATA ASSOCIATED WITH THE MT   Fixup

NUMBERS YOU HAVE
USED.
Fixup

Fixup

THIS PROGRAM CAN
BE ONLY DIRECTLY DEFINE RATIOS AND PRODUCTS       Fixup

USING TWO MT
NUMBERS = BINARY OPERATIONS, E.G., DEFINE THE CAPTURE Fixup

TO FISSION
RATIO, OR DEFINE THE PRODUCT NU-BAR*FISSION.
Fixup

Fixup

THIS PROGRAM
CANNOT DIRECTLY DEFINE RATIO OR PRODUCT OF A SUM OF   Fixup

SECTIONS TO THE
SUM OF ANOTHER SET OF SECTIONS. HOWEVER, THIS CAN  Fixup

BE DONE
INDIRECTLY BY FIRST DEFINING A DUMMY MT NUMBER (ANY MT     Fixup

NUMBER NOT
NORMALLY USED IN ENDF/B) TO BE A SUM OF SECTIONS AND    Fixup

A SECOND DUMMY
MT NUMBER TO BE A SECOND SUM OF SECTIONS. YOU CAN   Fixup

THEN DEFINE
RATIO OR PRODUCT YOU REQUIRE TO BE THE RATIO OF THESE  Fixup

TWO DUMMY MT
NUMBERS.
Fixup

Fixup

FOR EXAMPLE, TO
DEFINE ETA,
Fixup

1) FIRST DEFINE
(MT=27) = (MT=27) + (SUM OF MT=102 THROUGH 116)    Fixup

2) NEXT DEFINE
(MT=333) = (MT=452)*(MT=18)
Fixup

3) LAST DEFINE
(MT=255) = (MT=333)/(MT=27)
Fixup

DO NOT FORGET TO
TURN ON THE CREATE SECTION OPTION (ON THE FIRST   Fixup

INPUT LINE) AND
INPUT THE FIRST TWO LINES OF SECTION MT=255 -      Fixup

OTHERWISE YOU
WILL NOT GET ANY ENDF/B FORMATTED OUTPUT.
Fixup

Fixup

THE ONLY SPECIAL
CONVENTIONS USED BY THIS PROGRAM IN CALCULATING   Fixup

RATIOS ARE WHEN
THE DENOMINATOR OF THE RATIO IS ZERO. IN THIS      Fixup

CASE IF THE
NUMERATOR IS ALSO ZERO THE RATIO IS DEFINED TO BE ONE. Fixup

IN THIS CASE IF
THE NUMERATOR IS NOT ZERO THE RATIO IS DEFINED     Fixup

TO BE ZERO.
Fixup

Fixup

ENDF/B
FORMAT
Fixup

=============
Fixup

THIS PROGRAM MAY
BE USED WITH DATA IN ANY VERSION OF THE ENDF/B    Fixup

FORMAT (I.E.
ENDF/B-I, II, III, IV, V OR VI FORMAT). SINCE A       Fixup

PAGING SYSTEM IS USED STORE CROSS SECTION
TABLES ON SCRATCH FILES  Fixup

THERE IS NO
LIMIT TO THE SIZE OF TABLES (E.G. THE TOTAL CROSS      Fixup

SECTION MAY BE
REPRESENTED BY 200,000 TABULATED POINTS).
Fixup

Fixup

WARNING
Fixup

=======
Fixup

(1) FOR EACH
SECTION OF CROSS SECTIONS (I.E. EACH MT, MF=3) IN     Fixup

THE ORIGINAL EVALUATION (I.E. ENDF/B DATA READ) ONE SECTION    Fixup

OF DATA WILL BE OUTPUT, UNLESS THE SECTION HAS BEEN DELETED.   Fixup

THIS INCLUDES ANY SECTIONS WHICH ARE NOT PRESENT IN THE
Fixup

ORIGINAL EVALUATION, BUT THE USER INDICATES (BY INPUT) SHOULD  Fixup

BE CREATED.
Fixup

Fixup

THE PROGRAM WILL NOT OUTPUT ANY SECTION RECONSTRUCTED BY       Fixup

SUMMATION UNLESS THE CORRESPONDING SECTION (MT NUMBER) IS      Fixup

PRESENT IN THE ORIGINAL EVALUATION OR USER INPUT INDICATES     Fixup

SHOULD BE CREATED AND OUTPUT. THIS IS (A) BECAUSE THE
Fixup

PROGRAM CANNOT DEFINE THE PARAMETERS TO APPEAR ON THE FIRST    Fixup

TWO LINES OF THE SECTION, (B) TO AVOID OUTPUTTING TOO MUCH     Fixup

DATA WHICH THE USER MAY NOT BE INTERESTED IN.
Fixup

Fixup

(2) FOR ANY
SECTIONS THAT DO NOT APPEAR IN THE ORIGINAL DATA THE   Fixup

USER MAY SPECIFY THAT THEY BE DEFINED BY SUMMATION. ANY SUCH   Fixup

SECTION MAY BE USED BE DEFINE SUBSEQUENT SUMS, BUT THE SECTION
Fixup

ITSELF WILL NOT BE OUTPUT (E.G. GENERALLY MT=27 AND 101 ARE    Fixup

NOT
PRESENT IN EVALUATIONS. HOWEVER, THE BUILT-IN SUMMATION    Fixup

RULES OF THIS PROGRAM USES THE ENDF/B SUMMATION RULES TO       Fixup

DEFINE MT=27 AND 101, WHICH IN TURN ARE USED TO DEFINE THE     Fixup

NON-ELASTIC CROSS SECTION, MT=3. SECTIONS MT=27 AND 101 ARE    Fixup

NOT OUTPUT).
Fixup

Fixup

(3) ALL DATA IN
FILE 3 AND 23 MUST BE LINEARLY INTERPOLABLE. IF    Fixup

THE DATA IS NOT LINEARLY INTERPOLABLE THIS PROGRAM WILL
Fixup

TERMINATE.
Fixup

Fixup

PROGRAM
OPERATION
Fixup

=================
Fixup

ALL MAT NUMBER
ON AN ENDF/B TAPE ARE PROCESSED. EACH MAT IS
Fixup

TREATED
SEPARATELY. WITHIN EACH MAT, EACH SECTION BEFORE MF=3      Fixup

IS READ,
CHECKED/CORRECTED (BASED ON INPUT OPTIONS) AND OUTPUT.    Fixup

WHEN MF=3 IS
LOCATED ALL CROSS SECTIONS ARE READ, SECTIONS TO BE   Fixup

DELETED ARE
DELETED, SECTIONS WHICH ARE NOT PRESENTED AND USER     Fixup

INPUT INDICATES
SHOULD BE CREATED ARE CREATE, SECTIONS TO BE KEPT  Fixup

ARE
CHECKED/CORRECTED (BASED ON INPUT OPTIONS) AND WRITTEN TO A    Fixup

SCRATCH FILE.
NEXT, IF THE USER SPECIFIES THAT THEY SHOULD,
Fixup

SECTIONS ARE
RECONSTRUCTED. FINALLY ALL CROSS SECTIONS (OLD AND    Fixup

NEW) ARE OUTPUT.
WITHIN THE SAME MAT, EACH SECTION AFTER MF=3 IS   Fixup

READ,
CHECKED/CORRECTED (BASED ON INPUT OPTIONS) AND OUTPUT.       Fixup

Fixup

MF=3
Fixup

====
Fixup

THE TREATMENT OF
THE CROSS SECTIONS REQUIRES UP TO 4 PASSES FOR    Fixup

CROSS SECTIONS.
IN THE PROGRAM THEY CORRESPOND TO SUBROUTINES      Fixup

PASS1, PASS2,
PASS3 AND PASS4. THE ORIGINAL AND FINAL ENDF/B DATA  Fixup

FILES, 5 SCRATCH
FILES AND 3 IN CORE ARRAYS ARE USED. OPERATIONS   Fixup

PERFORMED DURING
EACH PASS ARE,
Fixup

Fixup

PASS1
Fixup

=====
Fixup

READ ALL CROSS
SECTIONS FROM ITAPE. DELETED ANY SECTIONS. CREATE   Fixup

ANY SECTIONS.
CHECK/CORRECT THEM AND WRITE THEM TO SCRATCH FILE.   Fixup

DATA IS READ
INTO ARRAY A, TRANSFERRED TO ARRAY C (AFTER EDITING)  Fixup

AND OUTPUT TO
ISCRC FROM ARRAY C.                                  Fixup

ITAPE  - UNIT ORIGINAL ENDF/B DATA IS READ
FROM.
Fixup

ISCRC  - SCRATCH UNIT THAT EDITED DATA IS
WRITTEN ON.
Fixup

TABA   - ARRAY INTO WHICH ORIGINAL DATA
IS READ.
Fixup

TABC   - ARRAY INTO WHICH EDITED DATA IS
TRANSFERRED TO AND
Fixup

FROM WHICH IT IS WRITTEN TO ISCRC.
Fixup

Fixup

PASS2
Fixup

=====
Fixup

IF A UNIFORM
ENERGY GRID IS REQUESTED IT IS CREATED DURING THIS    Fixup

PASS. FIRST ALL
OF THE CROSS SECTIONS FROM PASS1 ARE READ AND A    Fixup

UNIFORM ENERGY
GRID IS CREATED = ALL ENERGIES THAT ARE INCLUDED    Fixup

IN AT LEAST ONE
SECTION (MT) OF CROSS SECTIONS.
Fixup

ISCRA  - SCRATCH UNIT CONTAINING UNIFORM ENERGY
GRID.
Fixup

ISCRB  - SCRATCH UNIT CONTAINING UNIFORM ENERGY
GRID.
Fixup

ISCRC  - SCRATCH UNIT THAT EDITED DATA IS READ
FROM.
Fixup

TABA   - ARRAY CONTAINING UNIFORM ENERGY
GRID.
Fixup

TABB   - ARRAY CONTAINING UNIFORM ENERGY
GRID.
Fixup

TABC   - ARRAY CONTAINING EDITED
DATA.
Fixup

Fixup

THE UNIFORM
ENERGY GRID ENDS UP ON ISCRB. NEXT EACH SECTION OF     Fixup

CROSS SECTIONS
FROM PASS1 IS READ FROM ISCRC, INTERPOLATED TO      Fixup

THE UNIFORM
ENERGY GRID AND OUTPUT TO ISCRA. FINALLY ISCRA AND     Fixup

ISCRC ARE
SWITCH, SO THAT AT THE END OF THIS PASS THE DATA WILL    Fixup

AGAIN BE ON
ISCRC (EXACTLY AS AT THE END OF PASS1), WITH UPDATED   Fixup

POINT
COUNTS.
Fixup

ISCRA  - SCRATCH UNIT THAT UNIFORM ENERGY GRID
DATA IS WRITTEN ON. Fixup

ISCRB  - SCRATCH UNIT CONTAINING UNIFORM ENERGY
GRID.
Fixup

ISCRC  - SCRATCH UNIT THAT EDITED DATA IS READ
FROM.
Fixup

TABA   - ARRAY CONTAINING UNIFORM ENERGY
GRID DATA.
Fixup

TABB   - ARRAY CONTAINING UNIFORM ENERGY
GRID.
Fixup

TABC   - ARRAY CONTAINING EDITED
DATA.
Fixup

Fixup

PASS3
Fixup

=====
Fixup

SUMMATION CROSS
SECTIONS ARE DEFINED BY READING DATA FROM ISCRC    Fixup

AND MERGING THEM
ONTO ISCRA. THE FIRST SECTION THAT CONTRIBUTES    Fixup

TO A SUM IS
MERELY COPIED FROM C TO A. IF MORE SECTIONS WILL       Fixup

CONTRIBUTE TO
THE SUM THE DATA IN A IS TRANSFERRED TO B, A
Fixup

SECTION OF DATA
FROM C IS ADDED TO THE DATA IN B AND STORED IN     Fixup

A. THE CYLE OF
ADDED C AND B TO A, FOLLOWED BY MOVING A TO B       Fixup

IS CONTINUED
UNTIL ALL CONTRIBUTING SECTIONS HAVE BEEN ADDED.      Fixup

THE SUM IS THEN
COPIED FROM A TO D. IF NEWLY CONSTRUCTED SECTION   Fixup

IS REQUIRED FOR
ANY LATER SUMMUATIONS IT IS ALSO COPIED TO E.      Fixup

THE CYCLE OF
ADDED SECTIONS FROM C AND B TO A IS REPEATED FOR      Fixup

EACH REQUIRED
SUMMATION REACTION. IN ADDITION TO SECTIONS FROM     Fixup

C, AFTER THE
FIRST SUMMATION SECTIONS MAY ALSO BE ADDED TO A       Fixup

FROM E (THE
CONTRIBUTION OF NEW RECONSTRUCTED CROSS SECTIONS).     Fixup

WHEN ALL
REQUIRED SECTIONS HAVE BEEN RECONSTRUCTED THE NEW
Fixup

SECTIONS WILL BE
ON E AND THE ORIGINAL SECTIONS ON C.
Fixup

ISCRC  - SCRATCH FILE FROM WHICH ORIGINAL DATA
IS READ.
Fixup

ISCRA  - SCRATCH FILE ONTO WHICH SUM FOR ONE
SECTION IS WRITTEN.   Fixup

ISCRD  - SCRATCH FILE ONTO WHICH ALL SUM CROSS
SECTIONS ARE        Fixup

WRITTEN.
Fixup

ISCRE  - SCRATCH FILE ONTO WHICH ALL SUM CROSS
SECTIONS WHICH
Fixup

ARE REQUIRED FOR LATER SUMS ARE WRITTEN.
Fixup

ISCRB  - UTILITY SCRATCH FILE USED TO CREATE
SUM CROSS SECTIONS.
Fixup

TABA   - ARRAY INTO WHICH SUMS ARE
WRITTEN.
Fixup

TABB   - ARRAY INTO WHICH PARTIAL SUMS
ARE WRITTEN.
Fixup

TABC   - ARRAY INTO WHICH ORIGINAL DATA
IS READ.
Fixup

Fixup

PASS4
Fixup

=====
Fixup

CROSS SECTIONS
ARE READ FROM ISCRC (ORIGINAL) AND ISCRD (NEW)      Fixup

AND ARE WRITTEN
IN THE ENDF/B FORMAT ON OTAPE. THE BEGINNING OF    Fixup

EACH SECTION OF
ORIGINAL DATA IS READ FROM ISCRC (TO DEFINE
Fixup

SECTION HEADER INFORMATION). IF THIS MT
HAS NOT BEEN RECOSTRUCTED
Fixup

ON ISCRD THE
ORIGINAL SECTION IS OUTPUT. IF THE SECTION HAS BEEN   Fixup

RECONSTRUCTED
THE ORIGINAL SECTION IS SKIPPED AND THE NEW SECTION  Fixup

IS OUTPUT.
Fixup

OTAPE  - OUTPUT DATA IN THE ENDF/B FORMAT.
Fixup

ISCRC  - SCRATCH FILE FROM WHICH ORIGINAL DATA
IS READ.
Fixup

ISCRD  - SCRATCH FILE FROM WHICH NEW DATA IS
READ.
Fixup

TABC   - ARRAY INTO WHICH CROSS SECTIONS
ARE READ FROM SCRATCH
Fixup

AND WRITTEN TO OTAPE
Fixup

Fixup

I/O FILE
DEFINITIONS
Fixup

====================
Fixup

UNIT   DESCRIPTION
Fixup

====   ===========
Fixup

2    INPUT
PARAMETERS.
Fixup

3    OUTPUT
REPORT.
Fixup

10    ORIGINAL DATA IN THE ENDF/B
FORMAT.
Fixup

11    FINAL DATA IN THE ENDF/B
FORMAT.
Fixup

12    SCRATCH FILE
Fixup

14    SCRATCH FILE
Fixup

15    SCRATCH FILE
Fixup

16    SCRATCH FILE
Fixup

17    SCRATCH FILE
Fixup

Fixup

OPTIONAL
STANDARD FILE NAMES (SEE SUBROUTINE FILIO1 AND FILIO2)    Fixup

===============================================================    Fixup

UNIT  FILE NAME   FORMAT
Fixup

====  ==========  ======
Fixup

2   FIXUP.INP    BCD
Fixup

3   FIXUP.LST    BCD
Fixup

10   ENDFB.IN     BCD
Fixup

11   ENDFB.OUT    BCD
Fixup

12-17  (SCRATCH)   BINARY
Fixup

Fixup

INPUT LINES
Fixup

===========
Fixup

LINE  COLUMNS  FORMAT  DESCRIPTION
Fixup

====  =======  ======  ===========                                 Fixup

1    1-14     14I1   INPUT OPTIONS AS DESCRIBED
ABOVE.
Fixup

EACH COLUMN OF THE INPUT LINE CONTROLS      Fixup

ONE OF THE TESTS/CORRECTIONS DESCRIBED      Fixup

ABOVE. TESTS/CORRECTION 1-14 (NOT ALL       Fixup

IMPLEMENTED YET) CORRESPOND TO COLUMNS      Fixup

1-14 OF THIS INPUT LINE AND ARE TREATED     Fixup

AS FOLLOWS,
Fixup

= 0 - DO NOT PERFORM TEST/CORRECTION.       Fixup

= 1 - PERFORM TEST/CORRECTION.
Fixup

FOR MT EXCLUSION FROM THRESHOLD TESTS       Fixup

(COLUMN 2), DELETION (COLUMN 4), OR
Fixup

SUMMATION (COLUMN 5) THE INPUT OPTION       Fixup

MAY BE,
Fixup

= 1 - READ RULES FROM INPUT
Fixup

= 2 - USE BUILT-IN RULES
Fixup

2    1-60      A60   ENDF/B INPUT DATA FILENAME
Fixup

(STANDARD OPTION = ENDFB.IN)
Fixup

3    1-60      A60   ENDF/B OUTPUT DATA FILENAME
Fixup

(STANDARD
OPTION = ENDFB.OUT)
Fixup

4-M    1-5      FREE   CHARACTER (S,D,T,R,*) FOLLOWED BY
BLANK OR  Fixup

FORM   MT NUMBER
Fixup

- THE ALLOWED CHARACTERS ARE,
Fixup

- S OR BLANK = SUM (OR DIFFERENCES)
Fixup

- D = DELETE
Fixup

- T = NO THRESHOLD ENERGY CORRECTIONS       Fixup

- R = RATIO
Fixup

- * = PRODUCT
Fixup

6-72
FREE   UP TO 10 LOWER
AND UPPER MT RANGES WHICH
Fixup

FORM   WILL BE USED TO
DEFINE THE RECONSTRUCTED
Fixup

CROSS SECTION OR TO DEFINE MT RANGES WHICH  Fixup

ARE EXCLUDED FROM THRESHOLD TESTS.
Fixup

Fixup

EACH MT NUMBER IS DEFINED BY A CONTINUOUS   Fixup

STRING OF DIGITS, POSSIBILITY PRECEEDED BY  Fixup

A - (MINUS SIGN). EACH MT NUMBER MUST BE    Fixup

BLANK OR OTHERWISE (NOT A DIGIT) DELIMITED. Fixup

Fixup

COLUMNS 6-72 MAY CONTAIN STRINGS OF DIGITS  Fixup

THE FIRST DIGIT STRING OF EACH PAIR MAY BE  Fixup

PRECEEDED BY A - (MINUS SIGN).
Fixup

Fixup

EACH LINE WILL BE INTERPRETED AS FOLLOWS,   Fixup

Fixup

*SUMMATION
(OR DIFFERENCES)
Fixup

--------------------------
Fixup

COLUMNS 1-5 = S OR BLANK FOLLOWED BY THE    Fixup

MT NUMBER TO BE DEFINED BY
SUMMATION
Fixup

Fixup

COLUMNS 6-72 = UP TO 10 MT RANGE (PAIRS OF  Fixup

MT NUMBERS) TO BE USED TO DEFINED THE SUM.  Fixup

IF THE FIRST MT NUMBER OF A PAIR IS
Fixup

NEGATIVE THE RANGE OF MT NUMBERS IS
Fixup

SUBTRACTED - AT LEAST ONE RANGE MUST BE     Fixup

SPECIFIED.
Fixup

Fixup

*DELETIONS
Fixup

---------
Fixup

COLUMNS 1-5 = D FOLLOWED BY BLANKS
Fixup

Fixup

COLUMNS 6-72 CONTAIN UP TO 10 MT RANGE      Fixup

(PAIRS OF MT NUMBERS), EACH RANGE DEFINING  Fixup

A RANGE OF MT NUMBERS TO BE DELETED - AT    Fixup

LEAST ONE RANGE MUST BE SPECIFIED.
Fixup

Fixup

*EXCLUSION FROM THRESHOLD TESTS
Fixup

------------------------------
Fixup

COLUMNS 1=5 = T FOLLOWED BY BLANKS
Fixup

Fixup

COLUMNS
6-72 CONTAIN UP TO 10 MT RANGE      Fixup

(PAIRS OF MT NUMBERS), EACH RANGE DEFINING  Fixup

A RANGE OF MT NUMBERS WHOSE THRESHOLD       Fixup

ENERGY WILL NOT
BE CHECKED - AT LEAST ONE
Fixup

RANGE MUST BE SPECIFIED.
Fixup

Fixup

*RATIO                                       Fixup

-----
Fixup

COLUMNS 1-5 = R FOLLOWED BY THE MT NUMBER   Fixup

TO BE DEFINED BY A RATIO
Fixup

Fixup

COLUMNS 6-72 CONTAINS 2 MT NUMBERS TO BE    Fixup

USED TO DEFINE THE RATIO.                   Fixup

Fixup

*PRODUCT
Fixup

-----
Fixup

COLUMNS 1-5 = * FOLLOWED BY THE MT NUMBER   Fixup

TO BE DEFINED BY A PRODUCT
Fixup

Fixup

COLUMNS 6-72 CONTAINS 2 MT NUMBERS TO BE    Fixup

USED TO DEFINE THE PRODUCT.
Fixup

Fixup

CONVENTIONS
Fixup

-----------
Fixup

*UP TO 20 DELETIONS AND 20 SUMMATIONS OR     Fixup

RATIOS
OR PRODUCTS MAY BE SPECIFIED.
Fixup

*ONLY 1 EXCLUSION FROM THRESHOLD TESTS       Fixup

MAY BE SPECIFIED (THE 1 LINE MAY CONTAIN    Fixup

UP
TO 10 MT RANGES TO EXCLUDE FROM TESTS).
Fixup

*INPUT IS TERMINATED BY INPUTTNG 0 OR
Fixup

BLANK IN COLUMNS 1-72 (I.E. THE LAST
Fixup

INPUT LINE MUST BE BLANK).
Fixup

*THE UPPER LIMIT OF EACH RANGE MUST BE AT    Fixup

LEAST AS BIG AS THE LOWER LIMIT (IN
Fixup

ABSOLUTE VALUE).
Fixup

*FOR RECONSTRUCTION POSITIVE MT RANGES WILL  Fixup

BE ADDED TO THE SUM AND NEGATIVE MT RANGES  Fixup

WILL BE SUBTRACTED.                         Fixup

*IF INPUT OPTION 2 (FIRST INPUT LINE) IS     Fixup

0 THRESHOLD EXCLUSION IS NOT ALLOWED.       Fixup

*IF INPUT OPTION 4 (FIRST INPUT LINE) IS     Fixup

0 DELETIONS ARE NOT ALLOWED.
Fixup

*IF INPUT OPTION 5 (FIRST INPUT LINE) IS     Fixup

0 SUMMATIONS AND RATIOS ARE NOT ALLOWED.    Fixup

N-K
IF THE USER SPECIFIES THAT SECTIONS WHICH   Fixup

ARE NOT PRESENT IN THE ORIGINAL EVALUATION  Fixup

MAY BE CREATED, TWO LINES MUST BE INPUT FOR Fixup

EACH
SECTION TO BE CREATED. THE TWO LINES
Fixup

DEFINE (C1, C2, L1 AND L2) FOR EACH OF THE  Fixup

FIRST TWO LINES OF THE SECTION TO BE
Fixup

CREATED.
THE FIRST LINE ALSO DEFINES (MAT
Fixup

AND MT). (N1, N2) ARE ALWAYS ZERO ON THE    Fixup

FIRST LINE AND WILL BE CALCULATED BY THE    Fixup

PROGRAM
FOR THE SECOND LINE.
Fixup

FIRST    1-11     E11.4  ZA OF SECTION TO BE CREATED
Fixup

LINE    12-22     E11.4  AWRE OF SECTION TO BE CREATED
Fixup

23-33
I11   L1 OF SECTION TO
BE CREATED
Fixup

34-44
I11   L2 OF SECTION TO
BE CREATED
Fixup

45-48
I4    MAT OF
SECTION TO BE CREATED
Fixup

49-51
I3    MT OF SECTION
TO BE CREATED
Fixup

SECOND    1-11     E11.4  C1 OF SECTION TO BE CREATED
Fixup

LINE    12-22     E11.4  C2 OF SECTION TO BE CREATED
Fixup

23-33
I11   L1 OF SECTION TO
BE CREATED
Fixup

34-44
I11   L2 OF SECTION TO
BE CREATED
Fixup

*PAIRS OF LINES MAY BE IN ANY MAT/MT ORDER   Fixup

(E.G., THEY NEED NOT BE IN ASCENDING
Fixup

MAT/MT ORDER).
Fixup

*UP TO 50 PAIRS OF LINES MAY BE USED TO      Fixup

DEFINE SECTIONS TO BE CREATED. THE LIST     Fixup

IS TERMINATED WHEN THE FIRST LINE OF A      Fixup

PAIR CONTAINS A ZERO (OR BLANK) MAT AND/OR  Fixup

MT.
Fixup

M-N
IF THE USER SPECIFIES THAT ENERGIES WHICH   Fixup

ARE NOT PRESENT IN THE ORIGINAL EVALUATION  Fixup

MAY BE INSERTED, ONE LINE MUST BE INPUT FOR Fixup

EACH
ENERGY TO BE INSERTED.
Fixup

1-11    E11.4   ENERGY TO BE INSERTED
Fixup

12-15
I4     MAT IN
WHICH TO INSERT ENERGY = 0 = ALL     Fixup

16-18     I3     MT IN WHICH TO INSERT
ENERGY = 0 = ALL
Fixup

*UP TO 50 (ENERGY, MAT, MT) LINES MAY BE     Fixup

USED. THE LIST IS TERMINATED BY A BLANK     Fixup

LINE.
Fixup

*INPUT MAY BE IN ANY (ENERGY, MAT, MT)       Fixup

ORDER.
Fixup

*ENERGY POINTS CAN ONLY BE INSERTED WITHIN   Fixup

THE ORIGINAL ENERGY RANGE OF A SECTION -    Fixup

THIS OPTION CANNOT BE USED TO EXTEND THE    Fixup

CROSS SECTION EITHER BELOW OR ABOVE THE     Fixup

ORIGINAL TABULATED ENERGY RANGE.
Fixup

Fixup

EXAMPLE INPUT
NO. 1
Fixup

===================
Fixup

(1) USE OPTIONS
1-11 (ALL OPTIONS, EXCEPT INSERT ENERGY POINTS)    Fixup

(2) DELETE
MT=900 (FOR EXAMPLE PURPOSES ONLY)
Fixup

(3) DEFINE THE
FOLLOWING MT NUMBERS TO BE RECONSTRUCTED,
Fixup

(MT=  4) = THE SUM OF MT= 51
THROUGH  91
Fixup

(MT=103) = THE SUM OF MT=700 THROUGH 718 (NOT 719)
Fixup

(MT=104) = THE SUM OF MT=720 THROUGH 738 (NOT 739)
Fixup

(MT=105) = THE SUM OF MT=740 THROUGH 758 (NOT 759)
Fixup

(MT=106) = THE SUM OF MT=760 THROUGH 778 (NOT 779)
Fixup

(MT=107) = THE SUM OF MT=780
THROUGH 798 (NOT 799)
Fixup

(MT=101) = THE SUM OF MT=102 THROUGH 114
Fixup

(MT= 18) = (MT=19) + (MT=20 AND 21) + (MT=38)
Fixup

(IF TOTAL
FISSION, MT=18, IS NOT PRESENT, DEFINE    Fixup

IT BY SUMMING FIRST, SECOND, ETC. CHANCE - NOTE     Fixup

THAT THIS MUST BE DONE IN THIS ORDER, SINCE THE     Fixup

NEXT SUM INVOLVES USING MT=18.
Fixup

(MT= 27) = THE SUM OF MT= 18 AND 101
Fixup

(MT=101 RECONSTRUCTED ABOVE USED IN SUM).
Fixup

(MT=  3) = THE SUM OF (MT=4)+(MT=6-9)+(MT=16-17)+(MT=22-37)+   Fixup

(MT=41-45)
Fixup

(MT=4 AND 27 RECONSTRUCTED ABOVE USED IN SUM).      Fixup

(MT= 19) = (MT=18) - (MT=20 AND 21) - (MT=38)
Fixup

(DEFINE FIRST CHANGE FISSION BY SUBTRACTION TO      Fixup

ALLOW RESONANCE CONTRIBUTION FROM MT=18 TO BE       Fixup

INCLUDED IN MT=19).
Fixup

(MT=  1) = THE SUM OF MT=2
AND 3
Fixup

(MT=3 RECONSTRUCTED ABOVE USED IN SUM).
Fixup

(4) THRESHOLD ENERGIES
OF THE FOLLOWING MT NUMBERS WILL NOT BE      Fixup

TESTED OR CORRECTED.
Fixup

MT=1, 4, 18, 19, 91, 103 THROUGH 114.
Fixup

(5) DEFINE MT=254 TO
BE THE CAPTURE TO FISSION RATIO (MT=102/18)    Fixup

(6) CREATE
MAT=1300/MT=254 - NOTE, THIS IS NECESSARY IN ORDER TO    Fixup

HAVE THE CAPTURE TO FISSION RATIO OUTPUT IN THE ENDF/B FORMAT   Fixup

Fixup

NOTE, ON THE
FOLLOWING INPUT LINES THE CHARACTERS = ( ) + , HAVE   Fixup

BEEN USED ONLY
TO MAKE THE INPUT MORE READABLE - THESE CHARACTERS  Fixup

WILL BE SKIPPED
BY THE PROGRAM IN READING INPUT - THE RESULTS      Fixup

WOULD BE THE
SAME IF THESE CHARACTERS WERE OMITTED, AS LONG AS     Fixup

ALL OF THE MT
NUMBERS ARE DELIMITED, I.E., THERE IS AT LEAST ONE   Fixup

NON-DIGITAL
CHARACTER BETWEEN MT NUMBERS. NOTE, THAT - (MINUS      Fixup

SIGN) IS
IMPORTANT AND IS USED DURING INPUT TO DEFINE MT RANGES    Fixup

WHICH SHOULD BE
SUBTRACTED, E.,G., SEE THE DEFINITION OF MT=19.    Fixup

Fixup

READ FILE
/ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT     Fixup

Fixup

THE FOLLOWING 21
INPUT LINES ARE REQUIRED.
Fixup

Fixup

11111111111
Fixup

/ENDFB6/K300/LEAD.IN
Fixup

/ENDFB6/K300/LEAD.OUT
Fixup

D900
Fixup

4=( 51, 91)
Fixup

103=(700,718)
Fixup

104=(720,738)
Fixup

105=(740,758)
Fixup

106=(760,778)
Fixup

107=(780,798)
Fixup

101=(102,114)
Fixup

18=(
19, 19)+( 20, 21)+( 38, 38)
Fixup

27=( 18,
18)+(101,101)
Fixup

3=(  4,  4)+(  6,
9)+( 16, 17)+( 22, 37)+( 41, 45)
Fixup

19=(
18, 18)-( 20, 21)-( 38, 38)
Fixup

1=(  2,  3)
Fixup

T    (  1,
1) (  4,  4) ( 18, 19) ( 91, 91) (103,114)
Fixup

R254=(102/
18)
Fixup

(BLANK LINE TO TERMINATE SUMMATION/DELETION RULES)    Fixup

2.00400+ 3
0.00000+ 0
0
01300254
Fixup

0.00000+ 0
0.00000+ 0
0
0
Fixup

(BLANK LINE TO TERMINATE SECTION CREATION RULES)      Fixup

Fixup

NOTE, THE
DELETION AND THRESHOLD EXCLUSION LINES MAY APPEAR IN     Fixup

IN ANY ORDER.
HOWEVER, SUMMATION AND RATIO RULES MUST APPEAR IN    Fixup

THE ORDER IN
WHICH YOU WANT THEM TO BE EXECUTED - E.G., THE
Fixup

ABOVE INPUT WILL
FIRST RECONSTRUCT MT=4, WHICH CAN THEN BE USED    Fixup

TO CONTRIBUTE TO
THE FOLLOWING SUM TO DEFINE MT=3, WHICH IN TURN   Fixup

CAN THEN BE USED
TO CONTRIBUTE TO THE FOLLOWING SUM TO DEFINE      Fixup

MT=1. IF THE
ORDER OF THE INPUT LINES IS CHANGED SUCH THAT MT=3    Fixup

IS RECONSTRUCTED
BEFORE MT=4, THE ORIGINAL MT=4 WILL BE USED IN    Fixup

THE SUMMATION TO
DEFINE MT=3. THE SAME RULES APPLY TO CALCULATING  Fixup

RATIOS, IF
EITHER THE NUMERATOR OR DENOMINATOR IS TO BE DEFINED    Fixup

BY SUMMATION,
THIS SHOULD BE DONE BEFORE DEFINING THE RATIO BY     Fixup

INPUT
PARAMETERS.
Fixup

Fixup

EXAMPLE INPUT
NO. 2
Fixup

===================
Fixup

(1) USE OPTIONS
1-11 (ALL OPTIONS, EXCEPT INSERT ENERGY POINTS)    Fixup

(2) USE BUILT-IN
TABLES FOR SUMMATION/DELETION/THRESHOLD EXCLUSION Fixup

(THIS ONLY REQUIRES COLUMNS 2, 4 AND 5 TO BE SET =2 ON THE     Fixup

FIRST INPUT LINE. THE BUILT-IN RULES EXACTLY CORRESPOND TO     Fixup

THE INPUT ABOVE UNDER EXAMPLE NO. 1, EXCEPT THAT NO MT NUMBERS
Fixup

WILL BE DELETED.
Fixup

(3) IF NOT
PRESENT, CREATE MAT=1300/MT=1
Fixup

Fixup

USE THE STANDARD
FILE NAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE    Fixup

DONE BY LEAVING
THE SECOND AND THIRD INPUT LINES BLANK).
Fixup

Fixup

THE FOLLOWING 6
INPUT LINES ARE REQUIRED.
Fixup

Fixup

12122111111
Fixup

Fixup

Fixup

2.00400+ 3
0.00000+ 0
0
01300  1
Fixup

0.00000+ 0
0.00000+ 0
0
0
Fixup

(BLANK LINE TO TERMINATE SECTION CREATION RULES)      Fixup

Fixup

EXAMPLE INPUT
NO. 3
Fixup

===================
Fixup

(1) USE OPTIONS
1-10 (ALL OPTIONS PRESENTLY IMPLEMENTED, EXCEPT    Fixup

DO NOT ALLOW SECTION CREATION AND INSERT ENERGY POINTS).       Fixup

(2) USE BUILT-IN
TABLES FOR SUMMATION/DELETION/THRESHOLD EXCLUSION Fixup

(THIS ONLY REQUIRES COLUMNS 2, 4 AND 5 TO BE SET =2 ON THE     Fixup

FIRST INPUT LINE. THE BUILT-IN RULES EXACTLY CORRESPOND TO     Fixup

THE INPUT ABOVE UNDER
EXAMPLE NO. 1, EXCEPT THAT NO MT NUMBERS Fixup

WILL BE DELETED.
Fixup

(3) DO NOT
CREATE ANY SECTIONS.
Fixup

Fixup

READ FILE
/ENDFB6/K300/LEAD.IN AND WRITE /ENDFB6/K300/LEAD.OUT     Fixup

Fixup

THE FOLLOWING 3
INPUT LINES ARE REQUIRED.
Fixup

Fixup

1212211111
Fixup

/ENDFB6/K300/LEAD.IN
Fixup

/ENDFB6/K300/LEAD.OUT
Fixup

Fixup

EXAMPLE INPUT
NO. 4
Fixup

===================
Fixup

SAME AS EXAMPLE
NO. 3, ABOVE, EXCEPT INSERT AN ENERGY POINT AT     Fixup

THERMAL FOR ALL
REACTIONS WHICH SPAN THE THERMAL ENERGY RANGE.     Fixup

Fixup

USE THE STANDARD
FILE NAMES ENDFB.IN AND ENDFB.OUT (THIS CAN BE    Fixup

DONE BY LEAVING
THE SECOND AND THIRD INPUT LINES BLANK).           Fixup

Fixup

THE FOLLOWING 5
INPUT LINES ARE REQUIRED.
Fixup

Fixup

121221111101
Fixup

Fixup

Fixup

2.53000-
2   0  0
Fixup

(BLANK LINE TO TERMINATE ENERGY INSERTS)
Fixup

Fixup

WARNING                                                            Fixup

=======
Fixup

ALTHOUGH THIS
PROGRAM IS DESIGNED TO ALLOW REACTIONS TO BE DEFINED Fixup

BY ADDING OR
SUBTRACTING REACTIONS THE USER SHOULD ALWAYS TRY TO   Fixup

DEFINE REACTIONS
BY SUMMING TO AVOID NEGATIVE CROSS SECTIONS. FOR  Fixup

EXAMPLE, IT IS
POSSIBLE TO CALCULATE MT=3 AND DEFINE MT=1 AS THE   Fixup

SUM OF MT=2 AND
3 (THE RECOMMENDED APPROACH AS USED IN THE ABOVE   Fixup

INPUT).
ALTERATIVELY IT IS POSSIBLE TO CALCULATE MT=1 AND DEFINE   Fixup

MT=3 AS MT=1
MINUS MT=2 (THIS APPROACH IS NOT RECOMMENDED).
Fixup

Fixup

THE ONLY
BUILT-IN SUMMATION RULE THAT USES SUBTRACTION IS THE      Fixup

CALCULATION OF
THE FIRST CHANGE FISSION (MT=19) AS THE TOTAL       Fixup

FISSION (MT=18)
MINUS THE SECOND, THIRD AND FOURTH CHANGE FISSION  Fixup

(MT=20, 21, 38).
THIS HAS BEEN DONE TO ALLOW THE RESONANCE
Fixup

CONTRIBUTION,
CALCULATED BY MANY CODES AND INCLUDED IN MT=18,      Fixup

TO BE
CONSISTENTLY INCLUDED IN THE FIRST CHANCE FISSION.           Fixup

Fixup

=======================================================================
Fixup