Analytical Method for Processing Neutron Multigroup Transfer Cross Sections
Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 319-344
Technical Paper / dx.doi.org/10.13182/NSE92-A15482
Contributon Slowing-Down Theory
Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 345-367
Technical Paper / dx.doi.org/10.13182/NSE92-A15483
Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 368-378
Technical Paper / dx.doi.org/10.13182/NSE92-A15484
Fission Fragment Transport Effects on Heat Transfer in Fissioning Gases
Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 379-390
Technical Paper / dx.doi.org/10.13182/NSE92-A15485
Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 391-403
Technical Paper / dx.doi.org/10.13182/NSE111-391
Evaluation of the Unresolved Resonance Range of 238U 4-+n, Part II: Differential Data Tests
Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 404-414
Technical Paper / dx.doi.org/10.13182/NSE92-A15487
High-Resolution Fission Cross-Section Measurements of 235U and 239Pu
Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 415-421
Technical Paper / dx.doi.org/10.13182/NSE92-A15488
Six-Group Decomposition of Composite Delayed Neutron Spectra from 235U Fission
Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 422-432
Technical Paper / dx.doi.org/10.13182/NSE92-A15489