Fission product data for thermal reactors. Part 2. Users manual for EPRI-CINDER code and data

England, T.R.; Wilson, W.B.; Stamatelatos, M.G.

doi:10.2172/5232905

Cited by 15 publications

(4 citation statements)

References 3 publications

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“…Fission Product Correlation for UMLEQ. New lumped fission product correlations were developed for UMLEO by using more detailed calculations with the burnup code EPRI-CINDER [27]. These new correlations were developed for UMLEO for all four energy groups and yield excellent results when compared to EPRI-CINDER.…”

Section: L_edmentioning

confidence: 99%

The slightly-enriched spectral shift control reactor

Martin¹,

Lee²,

Larsen³

1991

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An advaaced converter reactor design utilizing mechanical spectral shift control rods in a conventional pressurized water reactor configuration is under investigation. The design is based on the principle that a harder spectrum during the early part of the fuel cycle will result in larger neutron captures in fertile 238U, which can then be burned in situ in a softer spectrunl later in the cycle. Preliminary design calculations performed during FY 89 showed that the slightly-enriched spectral shift reactor design offers the benefit nf substantially increased fuel resource utilization with the proven safety characteristics of the pressurized water reactor technology retained. Optimization of the fuel design and development of fuel management strategies were carried out in FY 90, along with effort to develop and validate neutronic methodology for tight-lattice configurations with hard spectra.During FY 91, the final year of the grant, the final SESSR design was determined, and reference design analyses were performed for the assemblies as well as the global core configuration, both at the beginning of cycle (BOC) and with depletion. The final SESSR design results in approximately a 20% increase in the utilization of uranium resources, based on equilibrium fuel cycle analyses. Acceptable pin power peaking is obtained with the final core design, with assembly peaking factors equal to less than 1.04 for spectral shift control rods both inserted and withdrawn, and global peaking factors at BOC predicted to be 1.4. In addition, a negative MTC is maintained for BOC, which is difficult to achieve with conventional advanced converter designs based on a closed fuel ;a cycle. The SESSR design avoids the need for burnable poison absorber, although they could be added if desired to increase the cycle length while maintaining a negative MTC. A number of challenging reactor physics questions remain, including the treatment of resonance absorption in tight lattice reactors such as the SESSR and the optima, control of SSCRs throughout the fuel cycle to optimize the product',on and subsequent burnup of plutonium.

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Section: L_edmentioning

confidence: 99%

The slightly-enriched spectral shift control reactor

Martin¹,

Lee²,

Larsen³

1991

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“…Appendix E shows graphical comparisons for three types of light water reactors. One is similar to TMI-2 and is included with more than one 10" 6 10" 4 10" 3 10" 2 10 10° 10 l 10 2 10 3…”

Section: Comparisons Of Generic Light Water Reactorsmentioning

confidence: 99%

TMI-2 decay power: LASL fission-product and actinide decay power calculations for the President's Commission at Three Mile Island

England¹,

Wilson²

1979

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CINDER Histogram core power history, Three Mile Island, Unit 2 . . 12 2 Total core decay power from actinides and fission products, Three Mile Island, Unit 2 3 Actinide and fission-product decay power components, Three Mile Island, Unit 2 4 Comparison of calculated decay power of TMI-2 with end-of-cycle equilibrium core . 5 Total (fission-product plus actinide) decay power fraction of operational core power vs cooling time • A-l ANS 5.1 Standard upper-bound absorption correction G max .... A-2 ANS 5.1 Standard fission-product de_ay power pulse functions . . A-3 Ratio of 239 Pu and 238 U nominal decay heating to 235 U nominalinfinite irradiation 36 A-4 Comparison of Standard F(t,°°) for 235 U (1978) with 1973 Standard 37 B-l Number of nuclides contributing 2l 0.5% of total actinide or fission-product decay power C-l TMI-2 gas fraction of total fission-product decay power .... 175 C-2 TMI-2 gas fractions of total fission-product density and curies.

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“…They are a set of computational modules that provide an accurate calculation of: (1) Reactor irradia'tion or burnup; (2) Isotopic inventory from spontaneous decay; (3) Isotopic inventory changes from fuel cycle processes; and (4) Editing.…”

Section: Introductionmentioning

confidence: 99%

SHIELD verification and validation report

Boman¹

1992

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DISCLAIMERThis report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, no;" any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the a_uracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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Fission product data for thermal reactors. Part 2. Users manual for EPRI-CINDER code and data

Cited by 15 publications

References 3 publications

The slightly-enriched spectral shift control reactor

The slightly-enriched spectral shift control reactor

TMI-2 decay power: LASL fission-product and actinide decay power calculations for the President's Commission at Three Mile Island

SHIELD verification and validation report

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