FPDCYS and FPSPEC: computer programs for calculating fission-product beta and gamma multigroup spectra from ENDF/B-IV data. [In FORTRAN]
Technical Report
·
OSTI ID:7307963
FPDCYS and FPSPEC are two FORTRAN computer programs used at the Los Alamos Scientific Laboratory (LASL), in conjunction with the CINDER-10 program, for calculating cumulative fission-product beta and/or gamma multigroup spectra in arbitrary energy structures, and for arbitrary neutron irradiation periods and cooling times. FPDCYS processes ENDF/B-IV fission-product decay energy data to generate multigroup beta and gamma spectra from individual ENDF/B-IV fission-product nuclides. FPSPEC further uses these spectra and the corresponding nuclide activities calculated by the CINDER-10 code to produce cumulative beta and gamma spectra in the same energy grids in which FPDCYS generates individual isotope decay spectra. The code system consisting of CINDER-10, FPDCYS, and FPSPEC has been used for comparisons with experimental spectra and continues to be used at LASL for generating spectra in special user-oriented group structures. 3 figures.
- Research Organization:
- Los Alamos Scientific Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 7307963
- Report Number(s):
- LA-NUREG-6818-MS
- Country of Publication:
- United States
- Language:
- English
Similar Records
Multigroup beta and gamma spectra of individual ENDF/B-IV fission-product nuclides
Application of a library of processed ENDF/B-IV fission-product aggregate decay data in the calculation of decay-energy spectra. [FITPULS, in FORTRAN for CDC computers]
PEFPYD: a library of aggregate fission-product decay data derived from ENDF/B-IV
Technical Report
·
Sun Oct 31 23:00:00 EST 1976
·
OSTI ID:7325324
Application of a library of processed ENDF/B-IV fission-product aggregate decay data in the calculation of decay-energy spectra. [FITPULS, in FORTRAN for CDC computers]
Technical Report
·
Fri Sep 01 00:00:00 EDT 1978
·
OSTI ID:6797305
PEFPYD: a library of aggregate fission-product decay data derived from ENDF/B-IV
Technical Report
·
Thu May 01 00:00:00 EDT 1980
·
OSTI ID:5293939
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
652016* -- Nuclear Properties & Reactions
A=220 & above
Theoretical-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AFTER-HEAT
BASIC INTERACTIONS
BETA DECAY
BETA SPECTRA
COMPUTER CODES
DECAY
ENERGY
F CODES
FISSION PRODUCTS
FORTRAN
GAMMA SPECTRA
INTERACTIONS
ISOTOPES
LEPTONIC DECAY
LOSS OF COOLANT
MULTIGROUP THEORY
NEUTRON TRANSPORT THEORY
PARTICLE DECAY
PROGRAMMING LANGUAGES
Q-VALUE
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
SPECTRA
TRANSPORT THEORY
WEAK INTERACTIONS
WEAK PARTICLE DECAY
220900 -- Nuclear Reactor Technology-- Reactor Safety
652016* -- Nuclear Properties & Reactions
A=220 & above
Theoretical-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AFTER-HEAT
BASIC INTERACTIONS
BETA DECAY
BETA SPECTRA
COMPUTER CODES
DECAY
ENERGY
F CODES
FISSION PRODUCTS
FORTRAN
GAMMA SPECTRA
INTERACTIONS
ISOTOPES
LEPTONIC DECAY
LOSS OF COOLANT
MULTIGROUP THEORY
NEUTRON TRANSPORT THEORY
PARTICLE DECAY
PROGRAMMING LANGUAGES
Q-VALUE
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
SPECTRA
TRANSPORT THEORY
WEAK INTERACTIONS
WEAK PARTICLE DECAY