Abstract
The Intermediate Energy Standard Neutron Field (ISNF) is currently being utilized as a dosimetry standard field in cross-section adjustment studies as a part of an ongoing reactor pressure vessel damage analysis program at ORNL. Also, it is under consideration as a CSEWG dosimetry benchmark. This study updates previously reported results by the authors (1979) with the inclusion of ENDF/B-V ISNF flux spectrum calculations. Several anomalies which became evident during these calculations are presented and discussed.
| Original language | English |
|---|---|
| Title of host publication | Trans. Am. Nucl. Soc. (USA) |
| Place of Publication | USA |
| Publisher | American Nuclear Society |
| Pages | 466 - 9 |
| Number of pages | 4 |
| Volume | 35 |
| ISBN (Print) | 0003-018X |
| State | Published - 1980 |
Bibliographical note
CSEWG dosimetry benchmark;dosimetry standard;reactor pressure vessel damage analysis;ENDF/B-V ISNF flux spectrum calculations;Keywords
- dosimetry
- neutron transport theory
- radiation protection
- shielding