Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel
This paper reviews the accuracy and precision of methods used by United States electric utilities to determine the actinide isotopic and element content of irradiated fuel. After an extensive literature search, three key code suites were selected for review. Two suites of computer codes, CASMO and ARMP, are used for reactor physics calculations; the ORIGEN code is used for spent fuel calculations. They are also the most widely used codes in the nuclear industry throughout the world. Although none of these codes calculate actinide isotopics as their primary variables intended for safeguards applications, accurate calculation of actinide isotopic content is necessary to fulfill their function.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5334979
- Report Number(s):
- BNL-52316; ON: DE92013703
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220300* -- Nuclear Reactor Technology-- Fuel Elements
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACTINIDES
BURNUP
BWR TYPE REACTORS
C CODES
CHEMICAL ANALYSIS
COMPUTER CALCULATIONS
COMPUTER CODES
CROSS SECTIONS
E CODES
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUELS
ISOTOPE RATIO
ISOTOPES
M CODES
MATERIALS
METALS
NUCLEAR FUELS
O CODES
OBRIGHEIM REACTOR
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
QUANTITATIVE CHEMICAL ANALYSIS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTOR PHYSICS
REACTORS
ROBINSON-2 REACTOR
ROWE YANKEE REACTOR
S CODES
SAXTON REACTOR
SPENT FUELS
T CODES
THERMAL REACTORS
VERMONT YANKEE REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZION-1 REACTOR
ZION-2 REACTOR
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220300* -- Nuclear Reactor Technology-- Fuel Elements
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACTINIDES
BURNUP
BWR TYPE REACTORS
C CODES
CHEMICAL ANALYSIS
COMPUTER CALCULATIONS
COMPUTER CODES
CROSS SECTIONS
E CODES
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUELS
ISOTOPE RATIO
ISOTOPES
M CODES
MATERIALS
METALS
NUCLEAR FUELS
O CODES
OBRIGHEIM REACTOR
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
QUANTITATIVE CHEMICAL ANALYSIS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTOR PHYSICS
REACTORS
ROBINSON-2 REACTOR
ROWE YANKEE REACTOR
S CODES
SAXTON REACTOR
SPENT FUELS
T CODES
THERMAL REACTORS
VERMONT YANKEE REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZION-1 REACTOR
ZION-2 REACTOR