Abstract
Three-dimensional neutron diffusion calculations are routinely performed in support of various NRC-sponsored reactor fuel testing programs conducted in the Power Burst Facility test reactor at the Idaho National Engineering Laboratory. The calculations are done with the PDQ-7-II program. Results obtained to date show that criticality is quite accurately predicted at various steady-state power levels. In addition, for one reactor configuration considered measured axial power distributions at three different radial locations compare well with the predicted distributions.
| Original language | English |
|---|---|
| Pages | 363-373 |
| Number of pages | 11 |
| State | Published - 1978 |
| Event | Proc of ANS Top Meet on Adv in React Phys, Pap - Gatlinburg, TN, USA Duration: Apr 10 1978 → Apr 12 1978 |
Conference
| Conference | Proc of ANS Top Meet on Adv in React Phys, Pap |
|---|---|
| City | Gatlinburg, TN, USA |
| Period | 04/10/78 → 04/12/78 |
Fingerprint
Dive into the research topics of 'THREE-DIMENSIONAL DIFFUSION THEORY ANALYSIS OF THE POWER BURST FACILITY.'. Together they form a unique fingerprint.Cite this
- APA
- Author
- BIBTEX
- Harvard
- Standard
- RIS
- Vancouver