Projections of ENDF/B Version V Performance for Fast and Thermal Reactors Using Sensitivity Coefficients

Conference · Mon Apr 10 00:00:00 EST 1978

OSTI ID:7062072

Weisbin, C. R. ^[1]; Marable, J. H. ^[1]; Hardy, Jr., J. ^[2]; McKnight, R. D. ^[3]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. Bettis Atomic Power Lab. (BAPL), West Mifflin, PA (United States)
3. Argonne National Lab. (ANL), Argonne, IL (United States)

Proposed reductions to ²³⁵U($$\bar{v}$$) and ²³⁵U(n, f) in the fast energy range have significant impact for uranium fueled fast critical assemblies. The long-standing LMFBR ²⁸c/⁴⁹f calculated overprediction is not resolved by proposed Version 5 cross section modifications for ²³⁸U(n, γ) and ²³⁹Pu(n, f). The upward evaluation for the ²³⁹Pu(n, f)/²³⁵U(n, f) ratio improves criticality predictions for Pu fueled fast assemblies. For thermal reactors, changes to the ²³⁸U resonance parameters significantly reduce the long-standing ²⁸ρ discrepancy. Reduced resonance capture in the 1 eV ²⁴⁰Pu resonance has significant implications for LWR fuel cycle studies.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bettis Atomic Power Lab. (BAPL), West Mifflin, PA (United States); Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Division of Reactor Research and Technology; Electric Power Research Inst. (EPRI), Palo Alto, CA (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 7062072
• Report Number(s): CONF-780401-10; TRN: 78-016148
• Resource Relation: Conference: American Nuclear Society Topical Meeting, Advances in Reactor Physics, Gatlinburg, TN, (United States), 10-12 Apr 1978; Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
FAST REACTORS
REACTOR KINETICS
NUCLEAR DATA COLLECTIONS
THERMAL REACTORS
SENSITIVITY
EPITHERMAL REACTORS
KINETICS
REACTORS
Nuclear Criticality Safety Program (NCSP)
Evaluated Nuclear Data File (ENDF)
Light-Water Reactor (LWR)
Cross Section Evaluation Working Group (CSEWG)
SENPRO
Liquid Metal Fast Breeder Reactor (LMFBR)
Neutron Cross Section
220100* - Nuclear Reactor Technology- Theory & Calculation