Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel

Technical Report · Sun Dec 01 04:00:00 EST 1991

DOI:https://doi.org/10.2172/10143291· OSTI ID:10143291

Horak, W C; Lu, Ming-Shih

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: USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 10143291
• Report Number(s): BNL--52316; ON: DE92013703
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
220300
99 GENERAL AND MISCELLANEOUS
990200
ACTINIDES
BURNUP
C CODES
COMPUTER CALCULATIONS
COMPUTER CODES
CROSS SECTIONS
E CODES
FUEL ELEMENTS
ISOTOPE RATIO
M CODES
MATHEMATICS AND COMPUTERS
O CODES
OBRIGHEIM REACTOR
QUANTITATIVE CHEMICAL ANALYSIS
RADIOISOTOPES
REACTOR PHYSICS
ROBINSON-2 REACTOR
ROWE YANKEE REACTOR
S CODES
SAXTON REACTOR
SPENT FUELS
T CODES
THEORY AND CALCULATION
VERMONT YANKEE REACTOR
ZION-1 REACTOR
ZION-2 REACTOR