SCALE-4 analysis of pressurized water reactor critical configurations. Volume 4: Three Mile Island Unit 1 Cycle 5
The requirements of ANSI/ANS-8.1 specify that calculational methods for away-from-reactor criticality safety analyses be validated against experimental measurements. If credit is to be taken for the reduced reactivity of burned or spent fuel relative to its original fresh composition, it is necessary to benchmark computational methods used in determining such reactivity worth against spent fuel reactivity measurements. This report summarizes a portion of the ongoing effort to benchmark away-from-reactor criticality analysis methods using relevant and well-documented critical configurations from commercial pressurized water reactors. The analysis methodology utilized for all calculations in this report is based on the modules and data associated with the SCALE-4 code system. This volume of the report documents a reactor critical calculation for GPU Nuclear Corporation`s Three Mile Island Unit 1 (TNU-1) during hot, zero-power startup testing for the beginning of cycle 5. This unit and cycle were selected because of their relevance in spent fuel benchmark applications: (1) cycle 5 startup occurred after an especially long downtime of 6.6 years; and (2) the core consisted primarily (75%) of burned fuel, with all fresh fuel loaded on the core outer periphery. A k{sub eff} value of 0.9978 {+-} 0.0004 was obtained using two million neutron histories in the KENO V.a model. This result is close to the known critical k{sub eff} of 1.0 for the actual core and is consistent with other mixed-oxide criticality benchmarks. Thus this method is shown to be valid for spent fuel applications in burnup credit analyses.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 71347
- Report Number(s):
- ORNL/TM-12294/V.4; ON: DE95010427; TRN: 95:015199
- Resource Relation:
- Other Information: PBD: Mar 1995
- Country of Publication:
- United States
- Language:
- English
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05 NUCLEAR FUELS
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
SPENT FUEL CASKS
SAFETY ANALYSIS
SPENT FUEL STORAGE
SPENT FUELS
CRITICALITY
TRANSPORT
BENCHMARKS
THREE MILE ISLAND-1 REACTOR
REACTIVITY
S CODES
MULTIPLICATION FACTORS
BURNUP
THEORETICAL DATA