Computer Programs
NESC0685 EMERALD-NORMAL
last modified: 01-MAR-1976 | catalog | categories | new | search |

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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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, USA

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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.