Fast Critical Experiment Data for Space Reactors
- Argonne National Laboratory, Idaho Falls, IL (United States)
Data from a number of previous critical experiments exist that are relevant to the design concepts being considered for SP-100 and MMW space reactors. Although substantial improvements in experiment techniques have since made some of the measured quantities somewhat suspect, the basic criticality data are still useful in most cases. However, the old experiments require recalculation with modern computational methods and nuclear cross section data before they can be applied to today's designs. Recently, we have calculated about 20 fast benchmark critical experiments with the latest ENDF/B data and modern transport codes. These calculations were undertaken as a part of the planning process for a new series of benchmark experiments aimed at supporting preliminary designs of SP-100 and MMW space reactors.
- Research Organization:
- Argonne National Laboratory, Idaho Falls, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Nuclear Energy Programs
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 6381071
- Report Number(s):
- CONF-870102-12; ON: DE87007005
- Resource Relation:
- Conference: 4. Symposium on Space Nuclear Power Systems, Albuquerque, NM (United States), 12-16 Jan 1987; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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