ANALYSIS OF BOILING REACTOR TRANSIENTS FOR THE ASSESSMENT OF REACTIVITY COEFFICIENTS
- Author
- Husebye, J.
- Published
- [Place of publication not identified] : [publisher not identified], 1962.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1962. - Physical Description
- microopaque : positive ; 8 x 13 cm
- Additional Creators
- Nulund, O.
- Summary
- Oscillation measurements performed on the HBWR, lst charge, were correlated with a theoretical model for small reactor transients to assess reactivity coefficients at operating conditions. From the results it was found that the fuel temperature coefficient is about 1.5 pcm/ deg C, the void coefficient is 0.048% per% void in fuel channiels, and the moderator temperature coefficient is about 40 pcm/ deg C. The HBWR-1 reactor has a rather low steam void content in the core at operating conditions. Therefore, the reactor is stable, and its dynamic behavior is governed mainly by slow effects such as temperature changes of the moderator. This influenced to some extent the construction of the mathematical model. Although the model is generally applicable to boiling water reactors, it should not be used directly for extremely slow or for fast reactor transients. (auth)
- Report Numbers
- KR-25
- Other Subject(s)
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- NSA number: NSA-17-002581
OSTI Identifier 4765676
Research organization: Norway. Institutt for Atomenergi, Kjeller.
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