Comparison of reactivity feedback models for the FFTF passive safety tests
Description
The FFTF Loss-of-Flow-Without-Scram Test from 50% power to natural circulation flow was analyzed with the SASSYS code using both the SASSYS reactivity feedback models and the semiempirical reactivity feedback equations for the FFTF oxide-fuel core. The experimental data for primary loop flow and reactor power were used as inputs to obtain the same fuel, sodium, and structure temperatures for both sets of reactivity feedbacks. A detailed comparison was made for each of the reactivity feedbacks: Doppler, sodium density, control rod expansion, axial fuel expansion, radial expansion, and bowing. The major differences between the SASSYS reactivity models and the FFTF reactivity equations were in the radial expansion and bowing feedback. The sensitivity of the results to the input for the SASSYS radial expansion and bowing model was investigated
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE88013580.
Files
Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- WHC-SA--0275
Conference
- Title
- Safety of next generation power reactors.
- Dates
- 1-6 May 1988.
- Place
- Seattle, WA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20008837
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CONTROL ELEMENTS; DEFORMATION; EXPANSION; EXPERIMENTAL DATA; FEEDBACK; FFTF REACTOR; FUEL ELEMENTS; REACTIVITY; REACTOR SAFETY; S CODES; SODIUM
- Descriptors DEC
- ALKALI METALS; COMPUTER CODES; DATA; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; METALS; NUMERICAL DATA; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.
- Secondary number(s)
- CONF-880506--21.