Applicability of ZPR Critical Experiment Data to Criticality Safety

Conference · Mon Sep 25 00:00:00 EDT 1995

OSTI ID:195725

Schaefer, R. W. ^[1]; Aumeier, S. E. ^[1]; McFarlane, H. F. ^[1]

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1. Argonne National Lab., Idaho Falls, ID (United States)

More than a hundred zero power reactor (ZPR) critical assemblies were constructed, over a period of about three decades, at the Argonne National Laboratory ZPR-3, ZPR-6, ZPR-9 and ZPPR fast critical assembly facilities. To be sure, the original reason for performing these critical experiments was to support fast reactor development. Nevertheless, data from some of the assemblies are well suited to form the basis for valuable, new criticality safety benchmarks. The purpose of this paper is to describe the ZPR data that would be of benefit to the criticality safety community and to explain how these data could be developed into practical criticality safety benchmarks.

• Research Organization: Argonne National Laboratory (ANL), Idaho Falls, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 195725
• Report Number(s): ANL/TD/CP-87945; CONF-9509297-1; ON: DE96005529; TRN: 96:008318
• Resource Relation: Conference: Nuclear Energy Agency (NEA) Expert Meeting on Experimental Needs in Criticality Safety, Albuquerque, NM (United States), 25-26 Sep 1995; Other Information: PBD: [1995]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CRITICALITY
BENCHMARKS
ZPR-3 REACTOR
NUCLEAR DATA COLLECTIONS
ZPR-6 REACTOR
ZPR-9 REACTOR
ZPPR REACTOR
SAFETY ANALYSIS
URANIUM 235
PLUTONIUM 239
DATA COVARIANCES
Nuclear Criticality Safety Program (NCSP)
Zero Power Reactor (ZPR)
Monte Carlo
Cross Section Evaluation Working Group (CSEWG)
Plutonium
Gauss-Markov Adjustment (GMADJ) Code
Fast Reactor Physics
Nuclear Data