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

Abstract

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.

Authors:
;
Publication Date:
Research Org.:
Brookhaven National Lab., Upton, NY (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10143291
Report Number(s):
BNL-52316
ON: DE92013703
DOE Contract Number:
AC02-76CH00016
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Dec 1991
Country of Publication:
United States
Language:
English
Subject:
22 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; 220300; 220100; 990200; THEORY AND CALCULATION; MATHEMATICS AND COMPUTERS

Citation Formats

Horak, W.C., and Lu, Ming-Shih. Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel. United States: N. p., 1991. Web. doi:10.2172/10143291.
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Horak, W.C., & Lu, Ming-Shih. Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel. United States. doi:10.2172/10143291.
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Horak, W.C., and Lu, Ming-Shih. Sun . "Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel". United States. doi:10.2172/10143291. https://www.osti.gov/servlets/purl/10143291.
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@article{osti_10143291,
title = {Literature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel},
author = {Horak, W.C. and Lu, Ming-Shih},
abstractNote = {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.},
doi = {10.2172/10143291},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Dec 01 00:00:00 EST 1991},
month = {Sun Dec 01 00:00:00 EST 1991}
}
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Technical Report:
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DOI:  10.2172/10143291
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  • ;
    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 ismore » necessary to fulfill their function.« less

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    Existence of actinide colloids provides an important mechanism in the migration of radionuclides and will be important in performance of a geologic repository for high-level nuclear waste. Actinide colloids have been formed during long-term unsaturated dissolution of spent fuel by groundwater. This article summarizes a literature search of actinide colloids. This report emphasizes the formation of intrinsic actinide colloids, because they would have the opportunity to form soon after groundwater contact with the spent fuel and before actinide-bearing groundwater reaches the surrounding geologic formations.

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    This report presents a review of past studies that have attempted to delineate measurable and/or possible impacts of photochemical oxidants on the forests of Eastern United States. Sources of oxidant precursors and subsequent long distance transport phenomena are reviewed and documented. A brief historical treatment of eastern white pine responses to air pollutants is followed by an up-to-date evaluations of current air pollution measurements and associated impacts. Potential threats to eastern forest tree species are reviewed through a comparison of various fumigation studies in laboratory and field situations. The concept of hidden injury is discussed as being a possible majormore » impact problem facing analysis of real losses. The authors present evidence that would suggest that many forest tree species indigenous to the Eastern United States may already be detrimentally impacted by previous high oxidant episodes. They further suggest that even more drastic and only long term reversible effects to the forest ecosystem will follow a trend of increasing oxidant air pollution in many major forested regions of this area of the United States.« less