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NEA-0573 LASER-PNC.

LASER-PNC, Neutron Spectra in Uniform Lattice with Burnup Calculation

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1. NAME OR DESIGNATION OF PROGRAM:  LASER-PNC.
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2. COMPUTERS
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Program name Package id Status Status date
LASER-PNC NEA-0573/01 Tested 01-DEC-1979

Machines used:

Package ID Orig. computer Test computer
NEA-0573/01 IBM 3033 IBM 3033
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The program computes the neutron  spectrum in a uniform lattice made up of cylindrical rods, cladding, and surrounding moderator. The LASER is based on modified versions of the slowing-down program MUFT and the thermalization transport theory program THERMOS. The program performs a burnup calculation for the lattice. The spatial distribution of burnup within the fuel  rods is explicitly calculated. This calculation accounts for the variation of the neutron flux in space and energy during each time step. A buckling and a boron poison search (criticality search) are  provided as options.
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4. METHOD OF SOLUTION

The methods used in solving the neutron transport equation are essentially those utilized by the MUFT and THERMOS programs. The depletion equations are solved by assuming a polynomial expansion for exponential functions. The non-linear effects in the burn-up equations are accounted for by computing the  rate of change of the neutron flux with time and by using the Runge-Kutta numerical procedure to recover the flux as a function of time. The production and loss of chain members during irradiation are evaluated by simple matrix algebra.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The maximum number of space points is 14, with a maximum of 5 points in the fuel region. The code is restricted to 4 mixtures (fuel, cladding, moderator, and non-absorbing heavy scatterer). The moderator can be either light water (Nelkin or free gas scattering kernel), or heavy water (Nelkin scattering kernel). The cladding material can be stainless steel, aluminium or zircaloy-2. The fuel can be a metal, oxide or cermet. The epithermal and fast energy ranges include 50 energy groups. The  thermal range includes 35 energy groups.
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6. TYPICAL RUNNING TIME

Execution time for no-burnup cases are approximately 2 minutes when the standard THERMOS iteration technique is used without extrapolation. For burnup problems the execution time is approximately 4 minutes per time step (in case of  CDC-6600, 1.5 minutes per time step) when the linear approximation to the burnup equation is used.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED AND AUXILIARY PROGRAMS

The thermal library data for LASER-PNC is generated by the BCD program. BCD is described in reference 1.
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9. STATUS
Package ID Status date Status
NEA-0573/01 01-DEC-1979 Tested at NEADB
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10. REFERENCES

- T. Kajiyama, R. Yumoto:
Improvement of Burnup Analysis Code (LASER) In Lattice Cell of Light Water Moderated Reactor, PNCT831-74-02, Tokai Works Semi-Annual Progress Report (1974).
- T. Kajiyama:
User's Manual for LASER-PNC (Draft), (June 1979).
NEA-0573/01, included references:
- G.C. Poncelet:
Burnup Physics of Heterogeneous Reactor Lattices
WCAP-6069, UC-34 (June 1965).
- G.C. Poncelet:
LASER - A Depletion Program for Lattice Calculations Based on MUFT
and THERMOS
WCAP-6073, UC-32 (April 1966).
- LASER, ACC No. 249.360
ACC Programming Note 74-7 (October 29, 1973).
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11. MACHINE REQUIREMENTS:  LASER-PNC needs at least 640k bytes of fast memory.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0573/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED

FACOM OS IV/F4 (equivalent to IBM OS/VS-II),   G-level compiler.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

T. Kajiyama
Plutonium Fuel Division
Tokai Works
Power Reactor and Nuclear Fuel Development Corporation
Tokai-mura, Ibaraki-ken, 319-11 Japan
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16. MATERIAL AVAILABLE
NEA-0573/01
File name File description Records
NEA0573_01.001 JCL AND INFORMATIONS 65
NEA0573_01.002 ENDF/B LIBRARY DATA 14770
NEA0573_01.003 LIBRARY PREPARATION PROGRAM 142
NEA0573_01.004 LASER-PNC SOURCE (F4,EBCDIC) 7251
NEA0573_01.005 SAMPLE INPUT FOR LASER-PNC 19
NEA0573_01.006 PRINTED OUTPUT OF LIB. PREP. PROGRAM 62
NEA0573_01.007 PRINTED OUTPUT OF LASER-PNC 17712
NEA0573_01.008 PUNCHED OUTPUT OF LASER-PNC 486
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: buckling, burnup, cladding, criticality searches, depletion, fuel rods, moderators, neutron spectra, reactor lattices, slowing-down, transport theory.