129I is a radioactive isotope generated during the fission reactions inside nuclear fuels, and released during reprocessing of spent fuels (mainly shearing and dissolution). 129I has a very long half-life, high solubility and mobility in water, and high volatility, so immobilization of 129I is a significant objective in management of nuclear wastes. In China, iodine from reprocessing facilities cannot be discharged to the ocean in liquid form. Gaseous iodine is adsorbed by silver adsorbents, and immobilized in the form of silver iodide (AgI) or silver iodate (AgIO3). The waste silver adsorbents are compressed and encapsulated into UC-C type waste containers (similar to waste glass containers), and can be disposed of in the future according to the characteristics of the waste package. However, AgI or AgIO3 is unstable under the reducing conditions of geological disposal repositories. Therefore, it may be a safer and proper solution by immobilizing 129I (> 95 vol%) into waste substrates with long-term constraint performance (> 100,000 a). The purpose of this review is to introduce 129I long-term confinement solutions, compare and analyze the advantages and disadvantages of various technical solutions and applicable conditions, and summarize the iodine loading capacity, retention rate and iodine leaching rate of different waste forms. Among them, the immobolized iodosodalite treated by hot isostatic pressure curing technology shows good chemical durability, low iodine leaching rate, and can maintain thermal stability in deep geological repositories. Therefore, it can be considered as one of the technical routes for fixing 129I in reprocessing plants in China.