Development of the activation analysis calculational methodology for the Spallation Neutron Source (SNS)
For the design of the proposed Spallation Neutron Source (SNS), activation analyses are required to determine the radioactive waste streams, on-line material processing requirements remote handling/maintenance requirements, potential site contamination and background radiation levels. For the conceptual design of the SNS, the activation analyses were carried out using the high-energy transport code HETC96 coupled with MCNP to generate the required nuclide production rates for the ORIHET95 isotope generation code. ORIHET95 utilizes a matrix-exponential method to study the buildup and decay of activities for any system for which the nuclide production rates are known. In this paper, details of the developed methodology adopted for the activation analyses in the conceptual design of the SNS are presented along with some typical results of the analyses.
- Research Organization:
- Oak Ridge National Lab., Computational Physics And Engineering Div., TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 634109
- Report Number(s):
- ORNL/CP-96528; CONF-980403-; ON: DE98004119; TRN: 98:009784
- Resource Relation:
- Conference: Radiation protection and shielding topical meeting: technologies for the new century, Nashville, TN (United States), 19-23 Apr 1998; Other Information: PBD: Mar 1998
- Country of Publication:
- United States
- Language:
- English
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