The Coupled Aspects of a Fast-Thermal Critical: ZPR-V
- Argonne National Lab. (ANL), Lemont, IL (United States)
ZPR-V is a zero-power, coupled fast-thermal critical assembly involving a dilute fast core and a H2O-moderated, enriched uranium thermal annulus. The two regions are coupled through a natural U isolation blanket. This facility is useful in studying some of the properties of dilute fast reactor systems as well as those of coupled fast-thermal power breeders. Recent emphasis has been on the latter aspect of the problem and an investigation of the coupled aspects of the system has been made. An important parameter in the coupling concept is the division of reactivity. This can be determined by means of fast fuel substitutions and 1/v poisoning of the thermal annulus in conjunction with theoretical calculations. Auxiliary information obtained in such a procedure is the fast fuel worth throughout the core and the prompt neutron lifetime of the whole system. A second important parameter, S1/S2, is the relative number of neutrons emitted per unit time due to fast and slow fissions. Information regarding this quantity can be obtained with the aid of U235 and U238 fission distributions. Measurements of the above parameters were made for the case of a U238:U235 atomic ratio of 5:1 in the fast core and a 1-in. isolation blanket. The fractions of reactivity in the fast core, blanket, and annulus are, respectively, 24, 14, and 61%; the prompt lifetime is 39.0 ± 3.0 microseconds sec; the ratio S1/S2 is 0.43.
- Research Organization:
- Argonne National Laboratory (ANL), Lemont, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- W-31109-ENG-38
- NSA Number:
- NSA-12-003206
- OSTI ID:
- 4347298
- Report Number(s):
- ANL-5775
- Country of Publication:
- United States
- Language:
- English
Similar Records
EXPERIMENTAL AND THEORETICAL STUDIES OF THE COUPLED FAST-THERMAL SYSTEM, ZPR-V
Critical Studies of a 450-Liter Uranium Oxide Fast Reactor Core (ZPR-III Assembly 29)
Neutron Energy Spectrum Measurements in Unmoderated Assemblies
Technical Report
·
Thu Oct 30 23:00:00 EST 1958
·
OSTI ID:4326064
Critical Studies of a 450-Liter Uranium Oxide Fast Reactor Core (ZPR-III Assembly 29)
Technical Report
·
Mon Oct 31 23:00:00 EST 1960
·
OSTI ID:4833613
Neutron Energy Spectrum Measurements in Unmoderated Assemblies
Journal Article
·
Thu Mar 31 23:00:00 EST 1960
· Nuclear Science and Engineering
·
OSTI ID:4191756
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BLANKETS
CRITICAL ASSEMBLIES
DISTRIBUTION
FAST NEUTRONS
FISSION
Fast Core
LIFETIME
MEASURED VALUES
NATURAL URANIUM
Nuclear Criticality Safety Program (NCSP)
POISONING
PROMPT NEUTRONS
Prompt Neutron
REACTIVITY
REACTORS
RESEARCH REACTORS
THERMAL NEUTRONS
Theoretical Calculations
Thermal Annulus
U235
U238
URANIUM
URANIUM 235
URANIUM 238
WATER MODERATOR
ZONES
ZPR-5
BLANKETS
CRITICAL ASSEMBLIES
DISTRIBUTION
FAST NEUTRONS
FISSION
Fast Core
LIFETIME
MEASURED VALUES
NATURAL URANIUM
Nuclear Criticality Safety Program (NCSP)
POISONING
PROMPT NEUTRONS
Prompt Neutron
REACTIVITY
REACTORS
RESEARCH REACTORS
THERMAL NEUTRONS
Theoretical Calculations
Thermal Annulus
U235
U238
URANIUM
URANIUM 235
URANIUM 238
WATER MODERATOR
ZONES
ZPR-5