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NESC0685 EMERALD-NORMAL

EMERALD-NORMAL, Routine Radiation Release and Dose for PWR Design Analysis and Operation Analysis

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1. NAME OR DESIGNATION OF PROGRAM:  EMERALD-NORMAL
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2. COMPUTERS
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Program name Package id Status Status date
EMERALD-NORMAL NESC0685/01 Tested 01-MAR-1976

Machines used:

Package ID Orig. computer Test computer
NESC0685/01 IBM 370 series IBM 370 series
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3. DESCRIPTION OF PROBLEM OR FUNCTION

EMERALD-NORMAL  is   designed
for the calculation of radiation  releases and exposures resulting
from normal operation  of a large pressurized  water reactor.  The
approach used is similar to an analog simulation of a real system.
Each component or volume in the plant which contains a radioactive
material is represented  by a subroutine which keeps  track of the
production, transfer,  decay, and  absorption of  radioactivity in
that  volume.  During  the  course of  the  analysis, activity  is
transferred from  subroutine to  subroutine in  the program  as it
would be  transferred from place to  place in the plant.   Some of
this  activity is  then  released to  the  atmosphere  and to  the
discharge  canal.  The  rates  of  transfer, leakage,  production,
cleanup, decay,  and release  are read  as input  to the  program.
Subroutines  are  also  included   which  calculate  the  off-site
radiation exposures  at various distances for  individual isotopes
and sums of isotopes.  The program  contains a library of physical
data  for  the  forty  isotopes  of  most  interest  in  licensing
calculations,  and other  isotopes can  be  added or  substituted.
Because of  the flexible  nature of  the simulation  approach, the
EMERALD-NORMAL program can be used for most calculations involving
the production and release of radioactive material.  These include
design, operation, and licensing studies.
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4. METHOD OF SOLUTION

Explicit  solutions  of   first-order  linear
differential equations are included.  In addition, a subroutine is
provided  which solves  a  set  of simultaneous  linear  algebraic
equations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Many    parameters
and systems  included in the  program, particularly  the radiation
waste-treatment system, are  unique to the PG&E  Diablo Canyon PWR
plant.
   Maxima of -
   50 isotopes
    9 distances
   16 angular sectors
    1 operating period
    1 reactor power level
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6. TYPICAL RUNNING TIME

Less than 2 minutes  is required to compile
and execute the sample problem.
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7. UNUSUAL FEATURES OF THE PROGRAM

The use of  FORTRAN IV language,
modular  design, generic  variable names,  and extensive  internal
comments  makes  EMERALD-NORMAL  easily adaptable  to  the  user's
particular models and problems.
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8. RELATED AND AUXILIARY PROGRAMS

Subroutine    SIMQ,   which    is
documented in IBM System 360  Scientific Subroutine Package (360A-
CM-30X), Version III, Program Manual  H20-0205-3, is included.  In
1974 an earlier code, EMERALD,  was divided into EMERALD (Revision
1), (NESC Abstract  546), used to assess  accidental releases; and
EMERALD-NORMAL,  for  assessing  conditions  and  releases  during
normal or near-normal operation of a PWR.  New features include an
expanded library with  isotopes of interest in  liquid releases, a
detailed  model  of  a radiation  waste-treatment  system,  and  a
routine for calculation of doses from liquid releases.
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9. STATUS
Package ID Status date Status
NESC0685/01 01-MAR-1976 Tested at NEADB
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10. REFERENCES

S. G. Gillespie  and W. K. Brunot,  EMERALD-NORMAL: A
Program for  the Calculation  of Activity  Releases and  Potential
Doses from  the Normal  Operation of  a Pressurized  Water Reactor
Plant, Revision 1, Volume 1 - Program Description, Pacific Gas and
Electric Company, December 1974.
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11. MACHINE REQUIREMENTS:  576K bytes of memory
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0685/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:   OS/360,370.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

                 S. G. Gillespie and W. K. Brunot
                 Mechanical and Nuclear Engineering Department
                 Pacific Gas and Electric Company
                 77 Beale Street
                 San Francisco, California  94106
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16. MATERIAL AVAILABLE
NESC0685/01
File name File description Records
NESC0685_01.001 SOURCE PROGRAM (F4) EBCDIC 4504
NESC0685_01.002 SAMPLE PROBLEM INPUT DATA EBCDIC 460
NESC0685_01.003 SAMPLE PROBLEM PRINTED OUTPUT 5305
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: dose rates, fission products, gamma radiation, power plants, pwr reactors, radioactivity.