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Home / Publications / Journals / Nuclear Science and Engineering / Volume 96 / Number 2

Volume 96

Number 2

Optimization of Core Reload Design for Low-Leakage Fuel Management in Pressurized Water Reactors

Young Jin Kim,* Thomas J. Downar, Alexander Sesonske

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 85-101

Technical Paper / dx.doi.org/10.13182/NSE87-A16369

Fission Rates and High-Energy Neutron Fluxes in the Purdue Fast Breeder Blanket Facility

Helio C. Vital,* F. M. Clikeman, K. O. Ott

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 102-111

Technical Paper / dx.doi.org/10.13182/NSE87-A16370

Resonance Self-Shielding near Zone Interfaces

S. C. Mo, K. O. Ott

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 112-121

Technical Paper / dx.doi.org/10.13182/NSE87-A16371

Nuclear Data for 235U, 238U, and 239Pu in the Unresolved Resonance Region

A. A. Vankov and V. F. Ukraintsev, N. Yaneva, S. Toshkov, A. Mateeva

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 122-136

Technical Paper / dx.doi.org/10.13182/NSE87-A16372

Thermocapillary-Induced Breakup of Molten Cladding Films

P. R. Henkel

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 137-144

Technical Paper / dx.doi.org/10.13182/NSE87-A16373

Estimation of Failed Sensor Outputs

J. Louis Tylee

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 145-152

Technical Paper / dx.doi.org/10.13182/NSE87-A16374

Some Aspects of the Forward Method for High-Order Sensitivity Analysis

Yigal Ronen

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 153-158

Technical Paper / dx.doi.org/10.13182/NSE87-A16375

Measurement and Status of Neutron Scattering on 1Li and 7Li Between 6 and 14 MeV

D. Schmidt, D. Seeliger, G. N. Lovchikova, A. M. Trufanov

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 159-167

Technical Note / dx.doi.org/10.13182/NSE87-A16376

Time Behavior of the Neutron Flux at the Vessel Boundary of a Boiling Water Reactor Power Plant

A. Cesana, M. Terrani, G. Sandrelli

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 168-170

Technical Note / dx.doi.org/10.13182/NSE87-A16377

GERES: A Code to Process MC2-II Data for Heterogeneous Fast Reactor Cell Calculation

M. Galli

Nuclear Science and Engineering / Volume 96 / Number 2 / June 1987 / Pages 171-172

Computer Code Abstract / dx.doi.org/10.13182/NSE87-A16378

 

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