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Title: DEVELOPMENT AND APPLICATION OF CONSENSUS STANDARDS IN CRITICALITY SAFETY IN THE USA.

Abstract

No abstract prepared.

Authors:
Publication Date:
Research Org.:
Los Alamos National Lab., NM (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
788285
Report Number(s):
LA-UR-01-5807
TRN: US0302094
DOE Contract Number:
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: Conference title not supplied, Conference location not supplied, Conference dates not supplied; Other Information: PBD: 1 Oct 2001
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CRITICALITY; SAFETY; USA; LANL

Citation Formats

T. P. MCLAUGHLIN. DEVELOPMENT AND APPLICATION OF CONSENSUS STANDARDS IN CRITICALITY SAFETY IN THE USA.. United States: N. p., 2001. Web.
T. P. MCLAUGHLIN. DEVELOPMENT AND APPLICATION OF CONSENSUS STANDARDS IN CRITICALITY SAFETY IN THE USA.. United States.
T. P. MCLAUGHLIN. Mon . "DEVELOPMENT AND APPLICATION OF CONSENSUS STANDARDS IN CRITICALITY SAFETY IN THE USA.". United States. doi:. https://www.osti.gov/servlets/purl/788285.
@article{osti_788285,
title = {DEVELOPMENT AND APPLICATION OF CONSENSUS STANDARDS IN CRITICALITY SAFETY IN THE USA.},
author = {T. P. MCLAUGHLIN},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Oct 01 00:00:00 EDT 2001},
month = {Mon Oct 01 00:00:00 EDT 2001}
}

Conference:
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  • It is a brief discussion of the origin of some of the safety standards and codes provides the background for the use of these guides for the efficient design of chemical laboratories, pilot plants and process units. The beneficial use of these tools in a typical research-oriented design/construction project was shown to be an integral part of the project responsibilities.
  • Criticality safety evaluations implement requirements to proof of sufficient sub critical margins outside of the reactor environment for example in fuel fabrication plants. Basic criticality data (i.e., criticality standards) are used in the determination of sub critical margins for all processes involving plutonium or enriched uranium. There are several criticality international standards, e.g., ARH-600, which is one the US nuclear industry relies on. The French Nuclear Safety Authority (DGSNR and its advising body IRSN) has requested AREVA NP to review the criticality standards used for the evaluation of its Low Enriched Uranium fuel fabrication plants with CRISTAL V0, the recentlymore » updated French criticality evaluation package. Criticality safety is a concern for every phase of the fabrication process including UF{sub 6} cylinder storage, UF{sub 6}-UO{sub 2} conversion, powder storage, pelletizing, rod loading, assembly fabrication, and assembly transportation. Until 2003, the accepted criticality standards were based on the French CEA work performed in the late seventies with the APOLLO1 cell/assembly computer code. APOLLO1 is a spectral code, used for evaluating the basic characteristics of fuel assemblies for reactor physics applications, which has been enhanced to perform criticality safety calculations. Throughout the years, CRISTAL, starting with APOLLO1 and MORET 3 (a 3D Monte Carlo code), has been improved to account for the growth of its qualification database and for increasing user requirements. Today, CRISTAL V0 is an up-to-date computational tool incorporating a modern basic microscopic cross section set based on JEF2.2 and the comprehensive APOLLO2 and MORET 4 codes. APOLLO2 is well suited for criticality standards calculations as it includes a sophisticated self shielding approach, a P{sub ij} flux determination, and a 1D transport (S{sub n}) process. CRISTAL V0 is the result of more than five years of development work focusing on theoretical approaches and the implementation of user-friendly graphical interfaces. Due to its comprehensive physical simulation and thanks to its broad qualification database with more than a thousand benchmark/calculation comparisons, CRISTAL V0 provides outstanding and reliable accuracy for criticality evaluations for configurations covering the entire fuel cycle (i.e. from enrichment, pellet/assembly fabrication, transportation, to fuel reprocessing). After a brief description of the calculation scheme and the physics algorithms used in this code package, results for the various fissile media encountered in a UO{sub 2} fuel fabrication plant will be detailed and discussed. (authors)« less
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