AMPX:  a modular code system for generating coupled multigroup neutron-gamma libraries from ENDF/B

Greene, N.M.; Lucius, J.L.; Petrie, L.M.; Ford, William E.; White, J. E.; Wright, R.Q.

doi:10.2172/7342486

Cited by 80 publications

(40 citation statements)

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“…The neutron crosssection data used in this study came from the CSRL library. This study included collapsing the original 218-group structure of the neutron cross sections in the CSRL library to 27 groups using the AMPX [Greene et al, 1976] code system.…”

Section: Methods and Datamentioning

confidence: 99%

Compliance Assessment Document for the Transuranic Wastes in the Greater Confinement Disposal Boreholes at the Nevada Test Site, Volume 2: Performance Assessment

Cochran¹,

Beyeler²,

Brosseau³

et al. 2001

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Intermediate depth disposal operations were conducted by the U.S. Department of Energy (DOE) at the DOE's Nevada Test Site (NTS) from 1984 through 1989. These operations emplaced highspecific activity low-level wastes (LLW) and limited quantities of classified, "special case" transuranic (TRU) wastes in 37 m (120-ft) deep, 3 m (10 ft) diameter Greater Confinement Disposal (GCD) boreholes.Four boreholes contain about 60,000 kg (132,000 lb.) of classified TRU waste packages, containing less than 330 curies of Plutonium-239. All of the TRU wastes emplaced in the GCD boreholes are classified for national security reasons and cannot be disposed of in the DOE's Waste Isolation Pilot Plant.The U.S. Environmental Protection Agency's (EPA's) 40 CFR 191 defines the requirements for protection of human health from disposed TRU wastes. This EPA standard sets a number of requirements, including probabilistic limits on the cumulative releases of radionuclides to the accessible environment for 10,000 years. This report presents the performance assessment (PA) that has been conducted to determine if disposal of TRU waste in the GCD boreholes complies with the EPA's 40 CFR 191 requirements.Sandia National Laboratories completed this PA using all available information and an Iterative PA Methodology, which focused work on uncertainty reduction in a cost-effective fashion that does not overestimate system performance and assured defensibility. The simplicity of the conceptual models of the GCD disposal system allowed them to be implemented in Microsoft ® Visual Basic™ macros in an Access™ database. This PA model is built from a mathematical expression for mass conservation that includes the operation of a number of transport processes, including dissolution, precipitation, reversible chemical sorption onto soil, advection, diffusion, dispersion, radioactive decay and ingrowth, plant uptake, and bioturbation. The mathematical model and implementing code was used to calculate a complementary cumulative distribution function of integrated normalized release to the accessible environment for 10,000 years and probability distributions of dose based on two exposure conditions for the 1,000 year individual protection requirements.The primary conclusions of this PA are that the disposal of TRU wastes in the GCD boreholes will, at most, result in minuscule doses to individuals, and that the GCD disposal system easily meets the EPA's 1985, 40 CFR 191 requirements for disposal of TRU waste. Further, there is a strong, reasonable expectation that actual system performance will be better than what is simulated in this PA.vi ACKNOWLEDGMENTS

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Section: Methods and Datamentioning

confidence: 99%

Compliance Assessment Document for the Transuranic Wastes in the Greater Confinement Disposal Boreholes at the Nevada Test Site, Volume 2: Performance Assessment

Cochran¹,

Beyeler²,

Brosseau³

et al. 2001

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“…The use of ENDF/B-V data allowed us to compare the numerical approach presented here with similar calculations performed with the system of codes AMPX (used by the nuclear industry^ which in its present version do not include a R-matnx description of the cross sections. To compare both approaches we select the unresolved region, because it is more important than the resolved region for the design described in Table 1, and the actinides " T Np, M 'Am, " 4 Cm, because they are the most shielded of each actinide element. …”

Section: W(et) = -(2) (3)mentioning

confidence: 99%

Cross Sections for Actinide Burner Reactors

Difilippo

1992

Nuclear Data for Science and Technology

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“…be reconstructed in thefollowing form;· ~(n) = ~O,O + x -~OS e + x 1 .~l -8 1T 3 SIN e e-i~ - The scalar flux is (2. 72) 31 The substitution of Equation (2.70) into Equation (2.65) yields the final form of the reduced functional.…”

Section: Applications In Reactor Physicsmentioning

confidence: 99%