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DOI 10.2172/10143291
Title Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel
Creator/Author Horak, W.C. ; Lu, Ming-Shih
Publication Date1991 Dec 01
OSTI IdentifierOSTI ID: 10143291; Legacy ID: DE92013703
Report Number(s)BNL--52316
DOE Contract NumberAC02-76CH00016
Other Number(s)Other: ON: DE92013703
Resource TypeTechnical Report
CoverageTopical
Resource RelationOther Information: PBD: Dec 1991
Research OrgBrookhaven National Lab., Upton, NY (United States)
Sponsoring OrgUSDOE, Washington, DC (United States)
Subject22 GENERAL STUDIES OF NUCLEAR REACTORS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; SPENT FUELS; QUANTITATIVE CHEMICAL ANALYSIS; REACTOR PHYSICS; COMPUTER CODES; FUEL ELEMENTS; BURNUP; M CODES; C CODES; T CODES; S CODES; ACTINIDES; O CODES; CROSS SECTIONS; E CODES; COMPUTER CALCULATIONS; ISOTOPE RATIO; VERMONT YANKEE REACTOR; ROWE YANKEE REACTOR; ROBINSON-2 REACTOR; OBRIGHEIM REACTOR; SAXTON REACTOR; ZION-1 REACTOR; ZION-2 REACTOR; RADIOISOTOPES
Description/AbstractThis 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.
Country of PublicationUnited States
LanguageEnglish
FormatMedium: ED; Size: 49 p.
AvailabilityOSTI; NTIS; INIS; GPO Dep.
System Entry Date2008 Jun 19

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