The determination of the thermal neutron and gamma fluxes at the Maryland University Training Reactor using thermoluminescent dosimetry
- University of Maryland, Department of Chemical and Nuclear Engineering, College Park, MD 20742 (United States)
Determination of the dose received by a material in a mixed gamma and neutron field is of paramount concern to any research reactor owner. This dose can be separated into three distinguishable parts using standard thermoluminescent dosimetry (TLD) responses: 1) thermal neutron dose, 2) fission gamma dose, and 3) fission product gamma dose. For the Maryland University Training Reactor (MUTR), these respective fluences were determined for each of the associated experimental facilities. Quantifying the magnitude of the gamma and thermal neutron exposures at various reactor power levels was accomplished using Li-6F and Li-7F TLDs, respectively. These two types of dosimetry were chosen given the following considerations: 1) there is no existing standard established for fluence determination in a mixed field, 2) the LiF TLDs have a wide range of sensitivity to radiation, from 0.01 mR to 10,000 R, and 3) LiF TLDs are easy to read given the proper equipment. Standardization of the gamma/neutron doses was accomplished using the 500,000 Rad/hr Co-60 gamma source also located at the University of Maryland. (author)
- Research Organization:
- General Atomics, San Diego, CA (United States)
- OSTI ID:
- 21165904
- Report Number(s):
- INIS-US-09N0295; TOC-20; TRN: US09N0307042484
- Resource Relation:
- Conference: 11. biennial U.S. TRIGA users' conference, Washington, DC (United States), 10-13 Apr 1988; Other Information: Country of input: International Atomic Energy Agency (IAEA); 4 refs, 7 figs, 8 tabs; Related Information: In: 11. biennial U.S. TRIGA users' conference. Papers and abstracts, 426 pages.
- Country of Publication:
- United States
- Language:
- English
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