HTGR Knowledge Base

Conference Article: Derivation of criteria for primary circuit activity in an HTGR

Su, S.D.; Barsell, A.W. (General Atomic Co., San Diego, CA (USA))

Abstract

This paper derives specific criteria for the circulating and plateout activity in the primary circuit for a 2170-MW(t) high temperature gas-cooled reactor-gas turbine (HTGR-GT) plant. Results show that for a design basis, (1) the circulating activity should be limited to 14,000 Ci Kr-88 (a principal nuclide) to meet both offsite dose and containment access constraint during normal operation and depressurization accidents, and (2) the plateout inventories for those important nuclides affecting shutdown maintenance should not exceed 10,000 Ci Ag-110m, 45,000 Ci Cs-134 and 130,000 Ci Cs-137. This paper presents bases and methodology for deriving such criteria and compares them with light water reactors.

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key words: cesium 134; cesium 137; contamination; dose rates; fission products; htgr type reactors; krypton 88; primary coolant circuits; radionuclide migration; safety standards; silver 110; beta decay radioisotopes; beta-minus decay radioisotopes; cesium isotopes; cooling systems; even-even nuclei; gas cooled reactors; graphite moderated reactors; intermediate mass nuclei; internal conversion radioisoto; isomeric transition isotopes; isotopes; krypton isotopes; nuclei; odd-even nuclei; odd-odd nuclei; radioactive materials; radioisotopes; reactor components; reactor cooling systems; reactors; silver isotopes;
Reference:
Specialists meeting on coolant chemistry, plate-out and decontamination in gas-cooled reactors Juelich, Federal Republic of Germany 2-4 December 1980
International Atomic Energy Agency, Vienna (Austria)
IWGGCR--2, pp:75-80