THE HALDEN BOILING HEAVY WATER REACTOR--HBWR (in German)
The HBWR is a natural circulation boiling water power reactor in which heavy water circulates by natural convection of the moderator-coolant. In 4 1/2 yrs of operation, it has had two different fuel charges. The first charge consisted of nearly 300 elements made up of a single rod of natural U canned in a balanced 2 S Al alloy. The second fuel charge consisted of 100 assemblies of sintered pellets of 1.5% enriched UO/sub 2/, canned with Zircaloy-2. The maximum power levels were 5 and 20 Mw for the first and second charge, respectively. The corresponding maximum temperatures were 150 and 230 un. Concent 85% C. The first part of the experimental program for the first fuel loading was devoted to reactor statics-- steam void reactivity and distortion in thermal neutron flux. The dynamic behavior was investigated by studying the response of nuclear power and primary and secondary pressure and fiow to introduced reactivity and steam load perturbations. The research program of the second loading is similar to the first, but with the addition of the application of an instrumented fuel channel. (J.S.R.)
- Research Organization:
- IFA-OECD-Halden Reactor Project, Halden, Norway
- NSA Number:
- NSA-17-022874
- OSTI ID:
- 4692464
- Journal Information:
- Atomwirtschaft (West Germany) Changed to ATW, Atomwirtsch., Atomtech., Journal Name: Atomwirtschaft (West Germany) Changed to ATW, Atomwirtsch., Atomtech. Vol. Vol: 8; ISSN ATWSA
- Country of Publication:
- Country unknown/Code not available
- Language:
- German
Similar Records
HBWR PHYSICS EXPERIMENTS
HBWR QUARTERLY PROGRESS REPORT, JANUARY-MARCH 1963
Related Subjects
BOILING
BUBBLES
CONVECTION
FLUID FLOW
FUEL CANS
FUEL ELEMENTS
HALDEN BHWR
HEAVY WATER COOLANT
HEAVY WATER MODERATOR
INSTRUMENTS
NEUTRON FLUX
OPERATION
PELLETS
POWER
POWER PLANTS
PRESSURE
REACTIVITY
REACTOR FUELING
REACTOR TECHNOLOGY
REACTORS
SINTERED MATERIALS
STEAM
THERMAL NEUTRONS
TRANSFER FUNCTIONS
URANIUM
URANIUM DIOXIDE
ZIRCALOY
ZONES