Applicability of ZPR Critical Experiment Data to Criticality Safety
Conference
·
OSTI ID:195725
- 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
- Country of Publication:
- United States
- Language:
- English
Similar Records
Derivation of Criticality Safety Benchmarks from ZPR Fast Critical Assemblies
Derivation of criticality safety benchmarks from ZPR fast critical assemblies
ZPR/ZPPR Critical Experiment Facilities and As-Built ZPR/ZPPR Models
Conference
·
Sat Nov 15 23:00:00 EST 1997
·
OSTI ID:555232
Derivation of criticality safety benchmarks from ZPR fast critical assemblies
Journal Article
·
Sun Nov 30 23:00:00 EST 1997
· Transactions of the American Nuclear Society
·
OSTI ID:552477
ZPR/ZPPR Critical Experiment Facilities and As-Built ZPR/ZPPR Models
Technical Report
·
Mon Apr 01 00:00:00 EDT 2024
·
OSTI ID:2506757
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BENCHMARKS
CRITICALITY
Cross Section Evaluation Working Group (CSEWG)
DATA COVARIANCES
Fast Reactor Physics
Gauss-Markov Adjustment (GMADJ) Code
Monte Carlo
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
Nuclear Data
PLUTONIUM 239
Plutonium
SAFETY ANALYSIS
URANIUM 235
ZPPR REACTOR
ZPR-3 REACTOR
ZPR-6 REACTOR
ZPR-9 REACTOR
Zero Power Reactor (ZPR)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BENCHMARKS
CRITICALITY
Cross Section Evaluation Working Group (CSEWG)
DATA COVARIANCES
Fast Reactor Physics
Gauss-Markov Adjustment (GMADJ) Code
Monte Carlo
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
Nuclear Data
PLUTONIUM 239
Plutonium
SAFETY ANALYSIS
URANIUM 235
ZPPR REACTOR
ZPR-3 REACTOR
ZPR-6 REACTOR
ZPR-9 REACTOR
Zero Power Reactor (ZPR)