{'fraction_non_alphanumeric': 0.023890784982935155, 'fraction_numerical': 0.010921501706484642, 'mean_word_length': 5.401746724890829, 'pattern_counts': {'":': 0, '<': 0, '<?xml version=': 0, '>': 0, 'https://': 0, 'lorem ipsum': 0, 'www.': 0, 'xml': 0}, 'pii_count': 0, 'substrings_counts': 0, 'word_list_counts': {'cursed_substrings.json': 0, 'profanity_word_list.json': 0, 'sexual_word_list.json': 0, 'zh_pornsignals.json': 0}}
Design and Investigation of Liquid Lead-Bismuth Test Irradiation Loop in Research Reactor


 The Lead-bismuth eutectic (LBE) test irradiation loop is an indispensable testing vehicle for the investigation of LBE-cooled reactor fuel. To make a water-cooled research reactor have the irradiation test capacity of LBE-cooled reactor fuel, a test irradiation loop is investigated and preliminarily designed by absorbing the design and operation experience of the domestic and international heavy liquid metal loop. Structural material corrosion, impurity blockage, polonium diffusion, and metal solidification in the loop are considered in the design process. Corresponding measures have been taken to ensure the safe operation and emergency capacity of the loop. The loop is a 1500KW facility consisting of a coolant system and auxiliary systems the other, operating in a wide temperature range of 250–480 °C, oxygen concentration 0.01–0.05 ppm. The coolant system is to remove the heat from the fuel surface due to irradiation. Auxiliary systems are for coolant chemistry control, emergency fuel cooling, polonium control, and parameter measurement. In this paper, the technological process, main design parameters, and system composition of the loop are described, and the parameters and selections of main equipment, instrument parameters are proposed. The investigation supplies a useful reference for further design of test irradiation loop systems and equipment.