ALPHN. Calculates Neutron Production in Canisters of High-level Waste
- Oak Ridge National Lab., TN (United States)
ALPHN calculates the (alpha,n) neutron production rate of a canister of vitrified high-level waste. The user supplies the chemical composition of the glass or glass-ceramic and the curies of the alpha-emitting actinides present. The output of the program gives the (alpha,n) neutron production of each actinide in neutrons per second and the total for the canister. The (alpha,n) neutron production rates are source terms only; that is, they are production rates within the glass and do not take into account the shielding effect of the glass. For a given glass composition, the user can calculate up to eight cases simultaneously; these cases are based on the same glass composition but contain different quantities of actinides per canister.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Civilian Radioactive Waste Management, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 138764
- Report Number(s):
- ESTSC-000566IBMPC00
- Resource Relation:
- Other Information: PBD: 1 Oct 1992
- Country of Publication:
- United States
- Language:
- English
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ALPHN: A computer program for calculating ([alpha], n) neutron production in canisters of high-level waste
Calculates Neutron Production in Canisters of High-level Waste