Experimental Studies on the Kinetic Behavior of Water Boiler Type Reactors
- North American Aviation, Inc., Canoga Park, CA (United States)
The KEWB Program is devoted to the study of the dynamic behavior of homogeneous type research reactors. The objectives of this program include studies to develop better and more complete understanding of phenomena which contribute to the kinetic behavior and the inherent safety of the water boiler reactor. The approach to the objectives has been to construct a prototype 50 kw homogeneous reactor with the necessary auxiliary apparatus and to study the transient behavior of the system as a function of the more significant parameters which affect this behavior. These include the amount of reactivity release, rate of reactivity release, initial core pressure, initial core temperature, initial reactor power, and void volume above the core.
- Research Organization:
- North American Aviation, Inc., Canoga Park, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- NSA Number:
- NSA-12-015064
- OSTI ID:
- 4306725
- Report Number(s):
- A/CONF.15/P/1079
- Country of Publication:
- United States
- Language:
- English
Similar Records
A Summary of Experimental Results of the Spherical Core Investigations in the KEWB Program
KINETIC EXPERIMENTS ON WATER BOILERS-"A" CORE REPORT-PART II. ANALYSIS OF RESULTS
THE RESPONSE OF A WATER BOILER REACTOR TO VERY FAST POWER TRANSIENTS AND LINEARLY INCREASING REACTIVITY INPUTS. WATER BOILER EXCURSIONS WITH AN INITIALLY FILLED CORE
Journal Article
·
Mon Jun 01 00:00:00 EDT 1959
· Nuclear Science and Engineering
·
OSTI ID:4243796
KINETIC EXPERIMENTS ON WATER BOILERS-"A" CORE REPORT-PART II. ANALYSIS OF RESULTS
Technical Report
·
Wed Jan 31 19:00:00 EST 1962
·
OSTI ID:4812669
THE RESPONSE OF A WATER BOILER REACTOR TO VERY FAST POWER TRANSIENTS AND LINEARLY INCREASING REACTIVITY INPUTS. WATER BOILER EXCURSIONS WITH AN INITIALLY FILLED CORE
Technical Report
·
Mon Sep 01 00:00:00 EDT 1958
·
OSTI ID:4309587
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
BOILING
CONTROL SYSTEMS
COOLANT LOOPS
DIAGRAMS
HOMOGENEOUS REACTORS
KEWB
Logarithmic channel
MODERATORS
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PRESSURE
Pressure pulse
REACTOR CORE
REACTOR SAFETY
REACTORS
RESEARCH REACTORS
STABILITY
TEMPERATURE
TRANSFER FUNCTIONS
TRANSIENTS
WATER COOLANT
ZONES
BOILING
CONTROL SYSTEMS
COOLANT LOOPS
DIAGRAMS
HOMOGENEOUS REACTORS
KEWB
Logarithmic channel
MODERATORS
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PRESSURE
Pressure pulse
REACTOR CORE
REACTOR SAFETY
REACTORS
RESEARCH REACTORS
STABILITY
TEMPERATURE
TRANSFER FUNCTIONS
TRANSIENTS
WATER COOLANT
ZONES